SOVIET ATOMIC ENERGY VOLUME 29, NUMBER 6

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• Publication Date: December 1, 1970
• Content Type: REPORT

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Volume 29, Number 6
December, 1970
SOVIET
ATOMIC
ENERGY?
ATOMHAH 3HEP11411
(ATOMNAYA ENERGIYA)
TRANSLATED FROM RUSSIAN
CONSULTANTS BUREAU, NEW YORK
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,
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SOVIET
ATOMIC
ENERGY
-
ovietAtomic Energy is a cover-to-cover translation of Atomnaya
Energiya, a publication of the Academy of Sciences of the USSR.
An arrangement with ivlezhdpnarodnaya Kniga, the Soviet book
export agency, Takes available both advance copies of the Rus-
- sian journal and original glossy' photographs and artwork; This
serves to decrease the necessary time lag between publication
of the original and publicaiiop of the translation and helps to im-
prove the'quality of the latter. The translation began with the first
-
issue of the Russian journal.
Editorial Beard of Atomnaya Energiyi:
Editor M. D. Millionshchikov
Deputy Director
I. V. Kurchatov Institute of Atomic Energy
Academy of Sciences of the USSR .
MOscow, USSR ?
Asso'ciate Editors: N. A. kolokol'tsoV
N.' A. Vlasov
A. I. Alikhanov
A. A. Bochvat'
N. A. Dollezhal'
V. S.-Fursov
, I. N. Golovin
V. E. Kalinin
A. K. Krasin
A. 1.1 Leipunskii
V. V. Matveev
G. Meshcheryakov
P. N. Palei
V. B. Shevchenko
D. L. Simonenko
V. I. Smirnov
A P.,.Vinogradov,
A. P. Zefirov
, Copyright ? 1971 Consultants Bureau,'New York a division of Plenuin Publishing
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SOVIET ATOMIC ENERGY
A translation of Atomnaya Energiya
Volume 29, Number 6 December, 1970
CONTENTS
Engl./Russ.
On the Sixtieth Birthday of Boris Sergeevich Dzhelepov, Corresponding Member of the
Academy of Sciences of the USSR
1177
Turbulent Heat and Mass Exchange ? M. D. Millionshchikov
1178
411
Special Aspects of the Deformation of Uranium Subjected to Tensile Stain at a Constant
Velocity ? A. I. Voloshchuk, V. F. Zelenskii, Yu. F. Konotop,
and Yu. T. Miroshnichenko
1184
416
Subbarrier Neutron Fission of Pu238 (BIT) ? S. B. Ermagambetov and G. N. Smirenkin
1190
422
Design of Cascades for Separating Isotope Mixtures ? N. A. Kolokol'tsov,
V. P. Minenko, B. I. Nikolaev, G. A. Sulaberidze, and S. A. Trettyak
1193
425
Storage of Multiply-Charged Ions in a Relativistic Electron Bunch
? M. L. Iovnovich and M. M. Fiks
1199
429
Energy Balance in the Plasma in Apparatuses of the "Tokamak" Type
? Yu. N. Dnestrovskii and D. P. Kostomarov
1205
434
REVIEWS
Thermodynamics of the Uranium?Carbon, Uranium?Nitrogen, and Plutonium?Carbon
Systems ? V. V. Akhachinskii and S. N. Bashlykov
1211
439
ABSTRACTS
Slowing Down of Resonance Neutrons in Matter. Communication 4 ? D. A. Kozhevnikov
and V. S. Khavkin
1220
448
Investigation of the Calibration Characteristics of a Radiation Thermodiverter in
High-Intensity Fields of Ionizing Radiations ? V. S. Karasev, S. S. Ogorodnik,
and Yu. L. Tsoglin
1221
449
Calculation of Photoneutron Distribution by Monte Carlo Method ? A. A. Morozov
and A. I. Khisamutdinov
1222
449
Precision System for the Determination of Oxygen by Fast Neutron Activation
? I. P. Lisovskii and L. A. Smakhtin
1223
450
VVR Reactor Semiautomatic Activation Analysis System ? I. P. Lisovskii,
L. A. Smakhtin, N. V. Filippova, and V. I. Volgin
1223
450
Method of Attenuating Radial Betatron Oscillations in Cyclic Accelerators
? L. A. Roginskii and G. F. Senatorov
1224
450
Permanent Electromagnet with Built-in Radioisotope Thermoelectric Direct Converter
? A. Kh. Cherkasskii and V. S. Makarov
1225
451
LETTERS TO THE EDITOR
Experimental Study of the Characteristics of the IR-100 Research Reactor
? L. V. Konstantinov, I. N. Martem'yanov, V. A. Nikolaev, A. A. Sarkisov,
V. F. Sachkov, A. V. Sobolev, S. V. Chernyaev, and I. S. Chesnokov
1227
453
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Effect of the Flow Velocity of a Vapor?liquid Mixture of Coolant, and of Vapor
Content, on Surface Heat-Transfer Coefficient in Boiling of Water Inside Tubes
CONTENTS
(continued)
Engl./Russ.
?F. F. Bogdanov
1229
454
Neutron Yield from Thick Targets Bombarded with 11.5 and 23.5 MeV Protons
? V. K. Daruga and E. S. Matusevich
1233
456
A Method of Determining the Iron Content of Corrosion Product Deposits
?B. A. Alekseev, N. N. Kozhenkov, and G. A. Koteltnikov
1235
458
Group Separation of Fission Products by the Chromatographic Method
? L. N. Moskvin and N. N. Kalinin
1236
458
Experimental Verification of the Radiation-Chemical Method for Producing
Tetrachloroalkanes ? A. A. Bear, P. A. Zagorets, V. F. Inozemtsev,
L. S. Maiorov, V. I. Slavyanov, G. A. Artyushov, I. F. Sprygaev,
and V. A. Novozhilov
1240
461
Use of Xenon Proportional Counter Escape Peaks for X-Ray Radiometric Analysis
of Tungsten in Ores ? N. G. Bolotova, V. V. Koteltnikov, and E. P. Leman
1243
463
Diagnostics of an Electron?Ion Bunch Using Bremsstrahlung ? M. L. Iovnovich,
V. P. Sarantsev, and M. M. Fiks
1245
465
Excitation of Radial Betatron Oscillations by a Longitudinal Accelerating Field
?Yu. S. Ivanov, A. A. Kuzt min, and G. F. Senatorov
1248
467
NEWS
Liege May 1970 International Symposium on Modern Electric Power Generating
Stations ?P. A. Andreev
1251
470
June 1970 Princeton Symposium on Plasma Stabilization by Feedback and Dynamical
Techniques ? D. A. Panov
1253
471
June 1970 Zakopane Symposium on Nondestructive Materials Testing Equipment and
Techniques Using Nuclear Radiations ? A.Maiorov
1256
413
The Saturn-1 Plasma Machine ? V. A.Suprunenko
1259
474
The Anglo-Soviet Plasma Physics Experiment ? V. V. Sannikov
1260
475
GKIAE?JINR Agreement on Scientific and Technical Collaboration ? V.Biryukov
1262
475
BRIEF COMMUNICATIONS
1263
476
INDEX
Author Index, Volumes 28-29, 1970
1267
Tables of Contents, Volumes 28-29, 1970
1273
The Russian press date (podpisano k pechati) of this issue was 11/16/1970.
Publication therefore did not occur prior to this date, but must be assumed
to have taken place reasonably soon thereafter.
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ON THE SIXTIETH BIRTHDAY OF BORIS SERGEEVICH
DZHELEPOV, CORRESPONDING MEMBER OF THE
ACADEMY OF SCIENCES OF THE USSR
The Editorial Staff of Atomnaya Energiya congratulate Boris Sergeevich Dzhelepov on his sixtieth
birthday and wish him health and s successful continuation of his scientific and organixational activities
on behalf of nuclear physics in the Soviet Union.
Translated from Atomnaya Energiya, Vol.29, No. 6, December, 1970.
o 1971 Consultants Bureau, a division of Plenum Publishing Corporation, 227 West 17th Street, New York,
N. Y. 10011. All rights reserved. This article cannot be reproduced for any purpose whatsoever without
permission of the publisher. A copy of this article is available from the publisher for $15.00.
1177
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TURBULENT HEAT AND MASS EXCHANGE
M. D. Millionshchikov UDC 523.542
Turbulent heat and mass exchange in layers close to a wall has been studied by many authors [1, 3].
This problem has become especially important since it was discovered that the usual approach would not
explain the observed heat and mass exchange for values of Prandtl's number P (the ratio of the molecular
coefficient of kinematic viscosity to the thermal conductivity v/K) much larger than unity.
Some materials for which these processes have been experimentally investigated have Prandtl num-
bers of order 3000 or more. Deissler [1] analyzed experimental data for a wide range of values of P (0.5-
3000), and developed a special theory of heat and mass exchange which, with the appropriate choice of cer-
tain constants, yields results in good agreement with experimental results in this range.
Deissler considers the laminar sublayer to be a region of interaction between molecular and turbulent
exchange characterized by the distance from the wall and the kinematic viscosity. A logarithmic profile is
used in the region of developing turbulence, and in this way a better quantitative description of the velocity
profile is obtained than when a linear profile is used in the laminar sublayer and a purely logarithmic pro-
file.
However this method does not yield a theory for the dependence of heat and mass transfer on Prandtl's
number including small values.
Deissler also described the variation of Nusselt's number for large Prandtl numbers by taking it to
be proportional to the Prandtl number raised to the power 1/4.
Another position was taken concerning heat and mass exchange by L. D. Landau and V. G. Levich [2].
Their theory agrees with that of P. L. Kapitsa [4, 51, in that they consider that there are stable liquid-mo-
tion waves in layers close to a wall. The thermal conduction is very low in the viscous layer for large
Prandtl numbers, and so the turbulent pulsations in this layer lead to turbulent transfer comparable to
molecular transfer at distances from the wall considerably smaller than the thickness of the hydrodynamic
laminar sublayer. Hence the thickness of the thermal (or diffusion) laminar sublayer, i.e., the layer in
which turbulent exchange may be neglected, is in general a function of the molecular thermal conductivity.
The very general assumptions of the theory can be stated as follows:
1) The longitudinal component of the pulsation velocity u' varies like the mean velocity, i.e., it is
proportional to the distance from the wall;
2) the pulsation frequency is independent of the distance from the wall;
3) the correlation between the transverse velocity component and the transverse transfer scale is in-
dependent of the distance from the wall.
Under these assumptions, the longitudinal velocity pulsations satisfy the relation [2]
V Y
* 60
where v* is the dynamic velocity and 60 is the thickness of the hydrodynamic laminar sublayer.
The transverse velocity component corresponding to heat and mass transfer, estimated from the con-
tinuity condition for the flow has, in the layer close to the wall, the order
(-47)2.
Translated from Atomnaya Energiya, Vol.29, No.6, pp.411-426, December, 1970. Original article
submitted August 28, 1970.
Ct. 1971 Consultants Bureau, a division of Plenum Publishing Corporation, 227 West 17th Street, New York,
N. Y. 10011. All rights reserved. This article cannot be reproduced for any purpose whatsoever without
permission of the publisher. A copy of this article is available from the publisher for $15.00.
1178
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=MUM rff.E=1:::11-=?MalLiii =621:11i?m-nan =BEER =Er:: =Eginil
iiiiiiiiiiiii INN Miumiii Ira'
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NRI IIIMIII li IIIIIIIIIII IIIIIIIIIII 1111?11111111=111111111=M111111111Maill
khP 1111 1111 III No minimmonomonnoluipumilmo
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---.0.:?
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IC I
-510-3 10_2 0-1 , ro ro2 10 104 105P
10-
10
Fig. 1. The Stanton number S vs the Prandtl number P for the Reynolds
number R = 10,000.
The transfer path in the transverse direction is proportional to v', i.e., it depends on y in the same
way as the transverse velocity component and is proportional to y2/60.
The transverse heat transfer is proportional to the product of the transverse velocity component and
the mean transverse transfer path:
X.r?v?o (*)
where XTis the turbulent thermal conductivity.
Determination of 60 from the relation
V "?-? V.150,
yields
x, = const v (er?
Now taking the distance y = (5`0 from the wall as the thickness for which the turbulent thermal conduc-
tivity is of the order x (the molecular thermal conductivity), we obtain V. G. Levich's formula
6;=co0P-1/4. (1)
This relation directly yieldsthe limit formula for the thermal conductivity law for large P [2] , which
is confirmed by Deissler's experimental data. No limit formula can be obtained for small or intermediate
values of P.
Before turning to new constructions, we recall that, for P = 1, the laminar and thermal layers have
the same thickness. We thus set c = 1 in (1), i.e., we have
8=60P71/4 for P> 1. (2)
For Prandtl numbers smaller than unity, both the tangential turbulent stresses and the turbulent
transfer of heat and mass are negligibly small within the limit 150 of the laminar sublayer.
Hence, for P > 1, the value of (5`0, which is the distance from the wall at which turbulent heat and mass
transfer begin, is equal to the thickness So of the hydrodynamic laminar sublayer:
=se, for P ao the following equations in [2] are valid in the range of comparatively high frequencies:
F in (1+ q2)
xi = 480 (a> a0). (10)
a2H2 VT;
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The limits of applicability of the equations given above are very sensitive to the parameters of the
plasma. Usually, Eqs. (10) are valid for the thermal conductivity coefficients at the initial stage of the dis-
charge while the temperature of the plasma is low. However, as the internal portion of the plasma pinch is
heated up, the collision frequencies begin to decrease, and we go over to Eqs. (9); after that we may even reach the
range of validity of Eqs. (8). The transition from one branch to the other does not occur simultaneously for the en-
tire pinch. Therefore, in order to calculate the coefficients of thermal conductivity at different points it is neces -
ary to use different equations. All this greatly complicates the problem, making its qualitative investigation diffi-
cult and allowing reliable quantitative results to be obtained only by means of numerical methods.
The factor y is included in the terms of Eqs. (1) and (2), which are connected with the current. This
factor allows a phenomenological description to be given of the resistance observed in the experiment. The
case y = 1 corresponds to the classical plasma resistance given by the Spitzer formula.
The initial and boundary conditions were chosen in the form
(x, 0) = uo (2? x2); T( x, 0) = Tio (2 ? x2) (j =1, e); (11)
x(1, 0= = 0.2 aR,HI ; T,(1, t)=-T0(/=i, e), (12)
where I is the total current in the plasma in kiloamperes. The radial density distribution of the plasma'
was assumed to be parabolic; n(x) = N(1 ? (1/2)x2).
Equations (1)-(3) with the complementary conditions (11), (12) were integrated on an electronic com-
puter. The time evolution of the electron and ion temperatures were investigated, as well as the dependence
of the steady-state values of these temperatures on plasma density, longitudinal magnetic field, total cur-
rent, and the dimensions of the plasma pinch. The results of the corresponding calculations are described
below. In these calculations it was assumed that the total current I was independent of time and was dis-
tributed over the pinch cross section according to the parabolic law f(x, 0) = 21(1 ? x2)71- at the initial time
in accordance with the conditions (11). Thus, in the given series of calculations the problem of current
penetration into the plasma during the initial stage of the process corresponding to an increase of the total
current with time was not considered. Under these assumptions the function t(x, t) and the current density
f(x, t) remain practically constant with time. A change in the electron and ion temperatures Toe and To on
the boundary over fairly wide limits (10 to 100 eV) had a very slight effect on the solution of the problem.
As far as the initial temperatures were concerned, they ceased to affect the solution after a time had elapsed
which was 4-5 times as short as the energy lifetime.
The Results of the Calculations
As an example, Figs. 1 and 2 show the results of the numerical solution of the problem formulated
above for parameter values corresponding to the parameters of the T-3 apparatus at the I. V. Kurchatov
Atomic Energy Institute [5-7]. In the calculations it was assumed that
R = 100, a = 12, H = 38, 1 = 110,
T.?-- 50 (j -= e).
Since the characteristic time of the process in this case is of the order of several tens of milliseconds, the
integration of the system (1)-(3) was carried out till t = 40 msec. During this time Te, Ti, and re practically
reach their steady-state values. The calculations were carried out for purely hydrogen plasma and for a
mixture of hydrogen and deuterium having relative concentrations 4 and id(p +d = 1). In the latter case
the yield of neutrons accompanying the d ? d reaction was determined.
The energy lifetime re was found according to the equation
(14)
(13)
where E is the thermal energy of the plasma; Q is the Joule heat released by the current. For purposes of
comparison with experiment the energy lifetime rei = EiQi-? of the ions was likewise calculated, where
Ei is the energy in the ions, and Qi is the heat flux from the ions to the wall. The density ndd of the neutron
yield and the total flux Qdd of neutrons from the plasma were determined from the equations [10];
ndd =Van2172/3 exp (32 ? 188- Ti-113);
Qdd= 4n2Ra2 nddxdx.
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Figure 1 shows the dependences of the ion and electron temperatures of the space coordinate x = r/a.
The dashed line shows the density ndd of the neutron yield resulting from the d?d reaction. For the chosen
value of plasma density the heat exchange between electrons and ions is relatively small, and therefore the
"detachment" of the electron temperature from the ion temperature takes place during the heating process.
Figure 2 shows the dependence of Te max, Ti max, and rei on time for the same plasma parameters.
The experimental curves for Ti max and rei were obtained on the T-3 apparatus. Good agreement between
the results of the theory and experimental data indicates a possible explanation of the energy balance of the
plasma in this case within the framework of classical concepts of heat exchange and losses, and substan-
tiates the conclusion of the theory concerning the necessity of considering confined particles in the trans-
port processes. Analogous calculations were carried out for the T-3 apparatus in other operating modes
with modified values of the longitudinal magnetic field and total current. The results obtained under these
conditions are in good agreement with experimental data.
The curves in Fig.2 indicate a comparatively rapid establishment of the steady state in apparatuses
of this type. In order to clarify the possibilities of ohmic heating of the plasma in such apparatuses the
investigation of the dependence of the limiting steady-state values of the quantities Te max, Ti max, and re
on the geometric dimensions of the plasma pinch and such parameters as the plasma density, the magnitude
of the longitudinal fields, and the magnitude of the current is of great interest. Certain results of the in-
vestigation of these dependences have been presented in Figs. 3-5.
Figure 3 shows the dependence of the steady-state values Te max and Ti max on density for hydrogen
plasma and for a mixture of hydrogen and deuterium. The shape of the curves may be interpreted as fol-
lows. With increasing plasma density the heat exchange between electrons and ions improves, and due to
the fixed total current the fraction of energy released per particle decreases. Both of these factors lead to
an abrupt decrease in Te with increasing N. The ion temperature first increases due to the improvement
of heat exchange, and then begins to decrease. This is clearly evident for curves 1 and 3, while for curve
2 the corresponding value of density lies beyond the limits of the diagram. Note that as a whole the ion
temperature is very "inert" to a change in the plasma parameters. Whereas the electron temperature in
Fig. 3 differs by a factor of 2-3 in different operating modes, the change in ion temperature is 20 to 30%.
Figures 4 and 5 show the dependences of the steady-state values of Te max, Ti max, and re on the
longitudinal magnetic field and the dimensions of the plasma pinch for hydrogen plasma at a constant value
of density N = 6 and a value of the quantity q(1,t) = 2.2. In plotting Fig. 4 the values of the geometric para-
meters were chosen in accordance with Eq. (13), while the current varied with the magnetic field in accor-
dance with the boundary conditions (12): I = 3.28H. Calculations show that in this case Te max, Ti max, and
re increase with increasing H and I according to a practically linear law.
In calculating the curves in Fig. 5 the magnetic field was fixed (H = 40), while the current and the large
radius R of the torus were varied along with the radius a of the plasma pinch: I = 12.6a, R = 7a. The shape
of the curves in Fig. 5 may be qualitatively interpreted as follows. The linear dependence of I on a is con-
nected with the decrease in current density with increasing a, which leads to a decrease of Te max. How-
ever, since with increasing a the losses via thermal conductivity decrease, it follows that Ti max (and es-
pecially re) increases under these conditions.
Figure 6 is similar to Fig. 2. This figure shows the calculations for a hypothetical large apparatus.
The time variations of the quantities Te max, Ti max, and re are shown for hydrogen plasma (43 = 1) having
a normal resistance (y = 1) and an anomalous resistance (y = 5). The characteristic time of the process is
equal to 800 msec in this case. The high plasma density provides for good heat exchange between electrons
and ions, and as a result the differences in their temperatures are insignificant. The temperature of the
ions in the central portion of the plasma pinch reaches 1800 eV y = 1, while for y = 5 it reaches 3000 eV.
The authors express their deep thanks to Academician L. A. Artsimovich for stating the problem and
discussing the results.
LITERATURE CITED
1. D. Pfirsch and A.Schiiter, Max Planck Institute, Rep. MPI/Pa/7/62 (1962).
2. V. D. Shafranov, Atomnaya Energiya, 19, 120 (1965).
3. A. A. Galeev and R. Z. Sagdeev, Zh.Eksperim.i Teor. Fiz., 53, 348 (1967).
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4. L. M. Kovryzhnykh, Zh.Eksperim.i Teor. Fiz., 56, 877 (1969).
5. L. A. Artsimovich et al., Report CN-24/B-1 at the Third Conference on Research in the Field of
Plasma Physics and Controlled Fusion Reactions [in Russian], Novosibirsk (1968).
6. L. A. Artsimovich et al., Report to the International Conference on Plasma Confinement in Closed
Systems [in Russian], Dubna (1959).
7. H. Peacock et al., ibid. [Russian translation].
8. Yu. N. Dnestrovskii and D. P. Kostomarov, ibid. [in Russian].
9. E. B. Kadomtsev, in: Problems of Plasma Theory [in Russian], No. 5, Atomizdat, Moscow, p.209.
10. L. A. Artsimovich, Controlled Fusion Reactions [in Russian], Fizmatgiz, Moscow (1961).
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REVIEWS
THERMODYNAMICS OF THE URANIUM ? CARBON,
URANIUM ? NITROGEN, AND PLUTONIUM ?CARBON SYSTEMS
V. V. Akhachinskii and S. N. Bashlykov UDC 621.039.542.3:541.11
The Uranium ? Carbon System
Heat Capacity at Low Temperature. Certain results of recent measurements of the low-temperature
heat capacity of uranium carbides are presented in Table 1.
The data for U2C3 and UC2 are in very good agreement, but for UC there is a certain difference, evi-
dently caused by the different composition of the samples. In [1, 2], in a measurements of the heat capacity
of UC, pieces of cast carbide were used, the carbon content in which only slightly exceeded the stoichio-
metric; moreover, in [1] the measurements were performed on a well characterized sample, and no cor-
rection was introduced for the small excess of bound carbon. In [2], however, acorrection was made for
the presence of UC2, but the influence of oxygen, the amount of which in the carbide was rather high (1.9
mole %), was not taken into consideration.
The authors of [4] recommend that the average value from [1, 2] be used for the heat capacity of UC.
The results of a measurement of the heat capacity of UC, U2C3, and UC1.94 in the interval 5-350?K [1,
4] are presented graphically in Fig. 1 [5].
Heat Capacity and Heat Content at High Temperature. Measurements of the true heat capacity of UC
and UC2, performed in [6] in an adiabatic calorimeter in the interval 373-473?K and in [7] on the determina-
tion of C of uranium monocarbide in the interval 300-900?K by the nonstationary system method with pulsed
heating of the sample with a laser beam, should be considered insufficiently accurate.
The new technique, using pulsed heating (details unknown), was used in [8] to measure the heat capacity
of a homogeneous sample of UC in the interval 600-2700?K. The systematic error of the method did not ex-
ceed 3-5%.
300
400
40
35
0 30
25
20
15
I 10
0
200 600 WOO 1400 1800 2200 2600
!
400 800 1200 1600 2000 2400 T, ?K
0 10 20 T, ?K
Fig. 1 Fig. 2
Fig. 1. Heat capacity of U2C3 (1), UC1.94 (2), and UC (3) at low temperature.
Fig. 2. Heat content of UC1.0 at high temperature: 0) [9]; A) [10].
CP ? =11 98 c al/mole ? deg
Translated from Atomnaya Energiya, Vol.29, No. 6, pp. 439-447, December, 1970, Original article
submitted March 6, 1970.
C 1971 Consultants Bureau, a division of Plenum Publishing Corporation, 227 West 17th Street, New York,
N. Y. 10011. All rights reserved. This article cannot be reproduced for any purpose whatsoever without
permission of the publisher. A copy of this article is available from the publisher for $15.00.
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15
60
50
11 40
- 30
20
1
10
X
200 500 800 1100 1400 1700 2000 2300 2600 T,
a-UG2 I 13-UG2
AH=2,49,
kcal/mole
32
30
tao 28
5.)
26
24
LI 12
20
18
16
14
200 400
600
800
1000 1200
1400
1600 1800 T,
Fig. 3. Heat capacity (a) and heat con- Fig. 4. Heat capacity of UC2: *) [13]; A)
tent (b) of UC1.9: A) [12]; 10) [13].
TABLE 1. Thermal Functions of UC, U2C3,
and UC2 at 298?K
c,c1 1Carbide
Aa)
71
u 2,0
. 6-8
0.
S?, cal/mole
? deg
1
'H;98.15 '' HO,
cal/mole
,
Presumed composi-
tion, mole%
'0
5)
..
c)
ct
Li
-
-1
12,11
11,84
14,28
14,03
2193
2159
IJC1,02, 0,0i
97,5 UC-1-2,5 UC1,9
[1]
[2]
U2C3
25,66
25,55
32,93
32,91
4829
4836
U2C3
75,3 U2C3+10,6UC
+4,1 UC1,9+9,9 C
[3]
[2]
a-
L-C2
14,46
14,52
14,50
16,30*
16,33*
16,31*
2513
2521
2522
72,05 UC2,o
+10,03 IOC+ 17,9 C
UCi dm
95,3 LTC/,31-I-4,7 UC
[1]
[3]
[2]
* The entropy of mixing, characterizing the random-
ness in the arrangement of the C1 and C2 groups, is
not included,
[12].
TABLE 2. Heat Capacity (in cal/mole deg
K) of UC at High Temperature
T ?K
,
Data
of [8]
Data -
of [10]
T ?K ,
Data
of [8]
Data
of [10]
300
500
700
_
13,80
12,00
13,59
14,19
900
1100
14,30
14,85
14,64
15,08
The heat capacity of the rnonocarbide can be calcu-
lated according to the results of measurements of the heat
content in the intervals 300-1500?K [9] and 1287-2481?K
[10], presented in Fig. 2, by the method of calorimetry of
mixing. The data of these studies are in good agreement
with the overlapping temperature interval and fit into the
general curve expressed by equation [11] of the type
HT- 11298 = a+ bT dT3?? . (1)
Table 2 presents for comparison the values of the heat
capacity of UC, obtained in [8] and calculated in [11] according
to the data of [10]. Table 3 presents the thermal functions of
UC, calculated in [11].
Variation of the heat content of UC1.93 in the interval 1484-2851?K and UC1.9,3 in the interval 400-1500?K
was determined in [12] and [13], respectively, by the method of calorimetry of mixing (Fig. 3). In the over-
lapping temperature interval, the values found for the change in the enthalpy coincide within the limits of
the experimental errors, but the values of the heat capacity differ substantially. Thus, according to the
data of [12], at 1490?K the heat capacity of UC1.93 = 23.8 cal/mole ? deg, while according to the data of [13]
it is equal to 21.2 cal/mole ? deg. Moreover, as can be seen from Fig. 4, the nature of the change in the heat
capacity also differs. In [11] the data of the two investigations are compared and presented in the form of
an equation of the type of (1). In Fig. 3 the sharp increase in the heat capacity of a-UC2 close to the point
of the CY -0 conversion is clearly visible.
The substantial increase in the heat capacity of UC2 (and UC) in the region of high temperatures,
which follows from the results of the measurements of [12], was the cause of the lack of confidence in these
data. However, the author of [11] believes that there is no basis for doubt, since the heat content of other
carbides was also measured, and in the case of TiC, ZrC, and TaC, an increase in the heat capacity was
found, while in the case of Hf C, NbC, and WC, it was not. Nonetheless, the results of measurements of the
content of UC2 above 1650?K should be treated with caution, since when UC2 is cooled in the interval 2038-
1650?K, there is frequently a precipitation of UC. Such precipitation probably occurred during the mea-
surements in [12], which was noted by the authors of [20], who recalculated the data of [12] on the assump-
tion that they pertain to a mixture of 0.055 UC + 0.945 UC1.91 + 0.07 C. This theoretically correct correc-
tion somewhat lowers the value of the heat capacity of UC2 but has little effect on the value of the free
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TABLE 3. Thermal Functions of UC 1.0* TABLE 4. Thermal Functions of UC1.90*
g
=
ca
8
no
P
fi; a)
no
F
I -
---,
C, cal/mole
? Seg
S?r, cal/mole
? deg
(Fi? ? F1;98)/T,
cal/mole ? deg
H0-'"
= u
298,15
0,0
11,98
14,15
14,15
500
2 618
13,59
20,82
15,58
700
5 402
14,19
25,50
17,78
900
8 285
14,64
29,12
19,91
1100
11 260
15,08
32,10
21,87
1300
14 320
15,58
34,66
23,64
1500
17 490
16,13
36,92
25,26
1700
20 780
16,77
38,98 .
26,76
1900
24 200
17,48
40,88
28,15
2100
27 780
18,27
42,67
29,45
2300
31 520
19,14
44,37
30,67
2500
35 440
20,10
46,01
31,83
2700
39 560
21,13
47,59
32,94
2823
42 200
21,81
48,55
33,60
* H 1-1;98.15 = -4.9624 103+14.315 T - 1.5130 ? 10-4
T2+3.5038 ?10-7 T3+ 2.0828 ? 105/T cal/mole (298?-
- 2.823?K) ? 0.4%.
r.,
500.
E-9
cal/mole
C`' cal/mole
P'
? deg
a.)
Aca
--c-,.
U ?
El. -8
up .
H98)/T,
cal/mole. deg
C4 -298,15
0,00
14,52
16,33
16,33
500
3321,3
17,49
24,77
18,13
700
6 900,9
18,23
30,79
20,93
900
10 618
18,99
35,46
23,66
1100
14 527
20,187
39,37
26,17
1300
18 730
21,94
42,88
28,47
1500
23 344
24,30
46,18
30,62
1700
28 493
27,29
49,40
32,64
1900
34 304
30,92
52,62
34,57
2038
38 766
33,80
54,89
35,87
p -2038
41 264
29,44
56,12
35,87
2100
43 089
29,44
57,00
36,48
2300
48 976
29,44
59,64
38,39
2500
54 864
29,44
62,14
40,19
2800
63 695
29,44
65,47
42,72
2
13-UC2
T 298 9
X 10-3 1'2+ 2,727-10-6 T3? 5,487.105/T
-1,873.104+ 29,44 T
* The entropy of ordering is not included.
energy. function FT? - H2?88/T. Moreover, the correction cannot be accurate, since it cannot be established
how much UC was precipitated during cooling in the calorimeter [12]. Taking the aforementioned into con-
sideration, the author of [11] did not introduce any corrections into the data of [12] in the calculation of the
thermal functions of UC (see Table 3) and UC2 (Table 4). However, the thermal functions of UC2 should ev-
idently be corrected by adding the configurational entropy of ordering, calculated in [20] and equal to 0.60
cal/mole ? deg, to the experimentally found entropy of UC2.
There is no information on the high-temperature heat capacity of U2C3. Considering the unusual be-
havior of UC and UC2, all attempts to estimate it will be extremely doubtful.
Enthalpy of Formation. The standard enthalpy of formation (6,Hf288) of uranium carbides was deter-
mined most accurately by the method of calorimetry of combustion. On the basis of mass spectrometric
measurements [14], we detected a pronounced dependence of the enthalpy of formation of substoichiometric
uranium monocarbide on the composition [21]. Therefore, samples with the composition UC0.996 and UC1.032
were taken for combustion, i.e., close to the stoichiometric. The enthalpies of formation were found equal
to -23.3 ? 0.9 and -28.0 ? 1.0 kcal/mole, respectively [14]. Considering the results of our measurements
[22] of the heats of formation of U308 and UO2, these quantities should be approximately 0.8 kcal more nega-
tive, i.e., AHf288 for UCI.00 = -24.0 ? 0.7 kcal/mole. The value of the enthalpy of formation of UC2 should
also be corrected according to the same principle. Evidently, the most reliable value if .6,Hf288 for UC1.80
= -21.6 ? 1.4 kcal/mole. In [22] the enthalpy of formation of U2C3 was found equal to -44.0 ? 2 kcal/mole.
Free Energy of Formation. Figures 5-7 present the results of high-temperature measurements of the
free energy of uranium carbides, obtained by different researchers, treated in [4]. The solid lines in Figs.
5 and 7 were constructed on the basis of the thermal function of UC1.0 and UC1.8 (see Tables 3 and 4) in such
a way that they passed through the most reliable values obtained by the calorimetric method at the tempera-
ture 298?K.
The performance of measurements in different and frequently very limited temperature intervals and
the substantial discrepancies between the results of different authors hinder a comparison of the data and
do not give sufficiently reliable values of the free energy of uranium carbides within a broad temperature
range. Noteworthy is the discrepancy in the values of the free energy, c alculated from the purely calori-
metric data and obtained by other methods. Analyzing the causes of this discrepancy, the authors of [4] hy-
pothesized that the entropy of uranium (S;88) may be equal not to 12, but to 14 cal/mole ? deg. One of the
causes of the discrepancy of the results of measurements of the vapor pressure may be an impurity of oxy-
gen, especially when the investigated material is taken in the form of a powder or pulverized between in-
dividual experiments. Evidently a great role in the measurements is played by kinetic factors, since the
processes of diffusion determine the concentration gradient.
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26
U +C = UCI.L.t-1
6 8
25
1.5 t kcal
24-
0
? 2
7
23_
3 ?
22
5
21
20-
19 -
18-
300 1000
(500
2000 T, ?K
53 3C + 2U = U2C3
52-
co 511-
r. 50
4
49
- - 42
'1.1 47
46
45
44
300 1000 1500 2009 T, ?K
3
126.5
0 128.0
Fig. 5 Fig. 6
Fig. 5. Free energy of formation of UC: 1) purely calorimetric method (H298
= -23.3 kcal/mole) [14]; 2) equilibrium of UC + UC2 and UC2 + C with liquid
bismuth [15]; 3) equilibrium of UC with liquid zinc [16]; 4) measurement of
the emf [16]; 5) the same [17]; 6) equilibrium UO2 + 4C = UC2 + 2C0 [18]; 7)
vapor pressure of uranium in the system U - C (AHv =128 kcal/mole) [19];
8) see text.
Fig. 6. Free energy of formation of 1J2C3: 1) purely calorimetric data (PH298
= -43.3 kcal/mole) [19]; 2) measurement of emf [23]; 3 and 4) see text.
TABLE 5. Thermal Functions of UN
?
T, K
C,, cal
r'
/mole, deg
1-1?T - Fq98,
cal/mole
S?, cal
/mole??deg
(Fir - I-1;8)/T,
cal/mole ? deg
298
11,43
0
14,97
14,97
500
13,07,
2 512
21,37
16,35
700
13,65
5 190
25,87
18,46
900
14,06
7 961
29,35
20,50
1100
14,45 .
1081!
32,21
22.,38
1300
14,88
13 743
34,66
24,09
1500
15,36
16 767
36,82 '
25,64
1700
15.91
19 893
38,77
27,07
1900
16,52
23 125
40,57
23,41
2100
17,20
26 506
42.26
29,62
2310)
17,95
30 021
43,86
30,31
2500
18,77 -
33 692
45,39
31,92
2700
19,66-
.37 534
46,87
32,97
2930
20,63
41 562
48,31
33,98
3125
21,79
46 333
49;94
35,12
method):
To calculate the free energy, according to the data
of evaporation, in addition to the activity of carbon it is
necessary to know the heat of evaporation of uranium
(,11v298?K)? Its values, determined in different studies in
the last ten years, vary from 117 to 126 kcal/mole. In
the latter studies, even higher values were obtained - up
to -130 kcal/mole; a value of 128 kcal/mole was used in
[4]. The free energy of uranium carbides calculated using
this value does not coincide with the energy-obtained ac-
cording to purely calorimetric data, and the difference, as
can be seen from the figures, comes to 1.5-2 kcal. This
almost systematic discrepancy is elminated if we take the
heat of evaporation of uranium equal to 126.5 kcal/mole.
For AFf of U2C3, the following equation, correct
within the interval 973-1173?K, was obtained in [23] (emf
AF 7U2C3= -43860 --7T kcal/mole.
The value of A Ff for U2C 3c an be calculated, using data for UC and UC2, from the equilibria
1J2C3= 0,738UCI,o, 1,242UCI,75 (at 2000? K); U2C3+ 0,78C --= 2UCI,8, (at 1790'K).
The corresponding values of A Ff for U2C 3are equal to -49.96 kcal/mole (at AHv? = 128 kcal/mole) and -52.0
kcal/mole [4]. On account of the absence of certain necessary thermal data for 1J2C 3, it is not known whether there
is agreement between the values obtained. However, it is clear that when AHv = 128 kcal/mole is used, the value
of A Ff for U2C3is too small, but it becomes more suitable lithe calculation is performed at AlIv? = 126.5 kcal/mole.
The Uranium - Nitrogen System
In this article we shall discuss only the thermodynamic properties of uranium mononitride, UN, on the
basis of the data of [26].
The heat capacity and heat content of UN were determined experimentally at low temperatures in [27,
28] and at high temperatures in [29, 30] (Fig. 8).
The results of both low-temperature measurements [27, 28] are in good agreement in most of the tem-
perature region, but in the interval 250-350?K there is a slight discrepancy. The values of Cp obtained in
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- 28
,902 27
? 26
25
ir 24
I 23
22 1
21
300 1000 1500 2000 2500T, ?K 500 1000 1500 2000 2000 T, K
Fig. 7 Fig. 8
Fig. 7. Free energy of formation of UC2; 1) purely calorimetric data [24]; 2) measure-
ment of emf [17]; 3) equilibrium of UC2 + C with liquid bismuth [15]; 4) the same [25];
5) measurement of emf [23]; 6) equilibrium 1J02 + UC2 = 4UC + 2C0 [18]; 7) vapor
pressure of uranium in the system U ? C (6,Hv = 128 kcal/mole) [19]; 8) see text (en-
tropy of randomization taken into consideration).
Fig. 8. Heat capacity of UN; 1) data of [31]; 2) [11]; 3) [31], [29]; 4(0)) [26]; 4(x)) [29];
5) [32]; 6) [30].
U + 1.9C = UC1.9
1.8 kca
?4
3
22
21
20
1"4 19
a)
-c)
? 18
,f;), 17
16
^ 15
14
13
U 12
11
? 10
[28] are somewhat higher and in better agreement with the high-temperature measurements of [29], and for
this reason are preferable.
Of the high-temperature measurements [29, 30], the data of [29] are better, since they were per-
formed in a broader temperature interval. The calculated curves obtained [31, 32] were constructed as a
result of a mathematical treatment of the experimental data [29, 30]. However, these curves do not coincide
with the latter.
The author of [26], using the equation recommended [11] for the calculation of the temperature de-
pendence of refractory compounds of the type of carbides, of the form
= c, c2T ?c3T2+ c4T-2 (2)
and the experimental data of [29], also constructed the curves cited in Fig. 8. It is in good agreement with
experimental data of [29] and almost parallel to the curve expressing the heat capacity of uranium mono-
carbide UC, cited in Fig. 8 for comparison.
Considering the similarity of the chemical bonds and the monotypic nature of the crystal lattices of
UN and UC, such parallelism of the curves of Cp for UN and UC seems logical and is an additional confirma-
tion of the curve constructed in [26].
The thermal functions of UN, calculated by the author of [26] using the formula that he obtained, as
well as the values of the heat capacity C and the entropy S at 298?K, determined in [28], are cited in Table
5 and are recommended.
The heat of formation of UN was determined by two methods;
1) by measurement of the heat liberated in the reaction
U N2 ---> UN;
2) by the calorimetric method of combustion in fluorine or oxygen. The values of the heat of forma-
tion, measured by the second method, are more negative. The cause of this discrepancy is not known.
. Evidently the data obtained by the first method are preferable [35, 36], since they were measured
under conditions that better correspond to the practical conditions and are close to the heat of formation
of UN, measured by the method of combustion in oxygen [37]. The average of the data of these three studies
[35-37] is equal to ?70.4 0.7 kcal/mole and is recommended for the heat of formation of UN.
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TABLE 7. Thermal Functions of PuC0.87*
TABLE 6. Heat Capacity of PuC0.87 at Low
Temperature
T,
C? cal/mole
P'
? deg
ST, cal/mole
? deg
? Hi,
cal/mole
10
0,33
0,15
1,07
30
2,22
1,29
25,09
50
4,10
2,88
89,05
100
7,35
6,84
384,4
150
8,95
10,14
794,3
200
10,20
12.90
1274,1
250
11,21
15,29
1810,3
298,15
12,03
17,33
2370,4
400 600 800 1000
Fig. 9. Heat capacity of PuC0.9; x)
data of [33]; 40) [34].
, ?
T K
C, cal
r'
/mole- deg
ST, cal
/mole ? deg
1-1:1, ? Fq98
cal/mole
?(F.? H;98YT,
cal/mole ? deg
298
11,794
17,300
0,0
17,300
500
12,413
23,543
2 443
18,657
700
13,040
27,819
4 988
20,693
900
13,671
31,172
7 659
22,662
1100
14,303
33,976
10 456
24,471
1300
14,935
36,417
13 380
26,125
1500
15,567
38,598
16 430
27,645
1700
16,200
40,585
19 607
29,052
1927
16,918
42,660
23 366
30,535
* The entropy of ordering is not included.
The Plutonium ? Carbon System
Low-Temperature Heat Capacity. According to the communica-
tion [34], the heat capacity of plutonium monocarbide with the composi-
tion PuC0.95 (49 atomic % carbon) was measured at Harwell. By
metallographic analysis, 6.3 mole % Pu2C3 was detected in it, so that
the "monocarbide" had a composition of PuC0.86. The smoothed out
results of the measurements are presented in Table 6. There are
no other data on the low-temperature heat capacity of plutonium car-
bides.
High-Temperature Heat Capacity. There is information only
on the heat capacity of PuC0.87, measured by the method of calori-
metry of mixing in the interval 425-1295?K [33]. The thermal func-
tions of PuC0.9 obtained are cited in Table 7.
It is scarcely possible to evaluate the heat capacity of Pu2C3
sufficiently reliably, since there are no data for compounds with such
a structure.
Enthalpy of Formation. It should be considered that the values of Alli298 for PuC0.77 and Pu2C3, ob-
tained by the method of calorimetry of combustion [38], were erroneous on account of the insufficiently
accurate characterization of the combustible substances.
V. V. Akhachinskii has proposed a new method of evaluating the heats of formation of plutonium car-
bides [39]. He has noted that if in carbides formed by chemically similar metals (for example, TiC, ZrC,
Hf C) the values of the parameter AHsubl.me/Tm.me = Ki are close, then the values of AHf2981VIeCtAlisubl.Me
= K2 and Alif298mec/Tm.me are also close where AHsubLme and Tm.me are the heat of sublimation (at
298?K) and the melting point of the metal forming the carbide, while AHf298mec is the heat of formation of
the carbide per g-atom of the metal. In the case of carbides of variable composition, Allf298 pertains to
the carbide with maximum carbon content. As a result of the enthalpy of formation, the value of Hf298 for
PuCo.879
Pu2C3, and PuC2 was estimated at ?14.5 ? 1.4, ?29.0 ? 2.9, and 14.5 ? 1.4 kcal/mole.
Free Energy of Formation. Recently the pressure of plutonium above two-phase systems "PuC"
Pu2C3 and PuC2 + C was measured by the vapor transfer method [40]. The Knudsen method has been used
[41] to investigate two-phase regions "PuC" Pu2C3 and Pu2C3 + C. The results of the measurements, per-
formed by two groups of researchers in overlapping composition regions, differed by no more than 10%.
The vapor pressure of plutonium above two-phase regions was expressed by the following equations;
?PuC#H-Pu2C3
Pu2C3+ C
PuC2_x-I-C
1g Patm = 5.116
lg Patm = 4.39
1g Pam= 3.618
18:,53
1907?K);
(3)
(4)
(5)
(1325?
20330T
1835? K);
(1366 ?
18723
(2017-2472?K),
where the first equation is the result of a treatment of the experimental studies [40, 41] by the method of
least squares. From these equations we can obtain expressions for the change in the free energy of the
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TABLE 8. Thermodynamic Functions of
Pu C0.87
following reactions, on the assumption that the carbon-tich
boundary of the monocarbide phase corresponds to PuC0.3,
with
low
Pu2C3
T,
Alif, cal
/mole
AS?, cal/mole
? deg
while is a stoichiometric phase a very
LIFf, cal/mole centration interval:
con-
(6)
(7)
(8)
(9)
300
500
700
900
1100
1300
1500
1700
1927
From Eqs.
?10400
?11110
?11220
?11540
?12000
?11700
?11330
?10870
?10240
(6) and
2,89
1,19
1,01
0,56
0,04
0,29
0,55
0,84
1,19
(7) it follows
2 ,5PuCo,9(soi)-'-> 1 5PuC1 ,5(Sol) + Pu gas'
?11260
?11 700 AF =86270 ? 23741T cai;
?11 930 PuCI,5(S01)?> 1.5C(soo + Pligas?
?12 050
?12 040 LIF= 93010 ? 20.09T cai;
?12 080
?12 160 PuC2-x(soi)?> (2?i)Csoi +Pugas,
?12300
?12530 AF = 85710 ?16.55T cal.
that
PuCo,s(soi)---> MC501+ Pugas,
AF = 90320 + 21,42Tcal (1366? 1835? K).
Calculations using the second law of thermodynamics give a value of 1111238 = 93.0 kcal for reaction
(9), which is in good agreement with the value calculated according to the third law of thermodynamics
and is equal to 93.4 kcal. Combining this value with the standard heat of sublimation of plutonium (83.0
? 1.0 kcal), we can find that the standard enthalpy of formation of plutonium monocarbide Alli298 for
PuC (s01) = ?10.4 kcal/mole.
In [42] the activity of plutonium in the two-phase regions PuC + Pu2C3 (971-1060?K) and Pu2C3 + C
(974-1091?K) was measured by the emf method. Analyzing the results obtained, the author of [34] obtained
for the reaction
the equation
PUhci 1- 0.9es, PUG? ,9(sol)
(10)
AF= ? 15450 ? 1.30T cal (970 ? 1060? K), (11)
which differs somewhat fromthat cited in [42]. Evidently the slope of the line AF = f(T) according to the
data of [42] is erroneous, since the value of AS of the reaction could not be determined accurately on account
of the small temperature interval of the measurements. Calculations according to the third law, if A F1000,
calculated according Eq. (11), is taken as the basis, give a value of AHi238 for PuC0.3 = 12.5 kcal, which is
close to the value obtained by V. V.Akhachinskii [39] as a result of an estimate.
For the reaction
2Pu lig +3Csor= Pu2C3 (so))
(12)
the following function was found in [42]
= ?52500+ 14.7T cal (974-1091?K). (13)
At the present time, the results of measurements of the vapor pressure are preferable to the data ob-
tained by the emf method on account of the good agreement of the results of various investigators and the
good agreement with the theoretical data. Combining the latter with the calculated standard heat of forma-
tion of PuCO3 (-10.4 kcal/mole), we can obtain the thermodynamic functions cited in Table 8.
The free energy of formation can be represented by two equations:
Pusoi + 0 .9Qoi= PuC0,9(s01),
AF? = ? 11060 ? 1.16T (298 ? 913? K);
Puhq+0.9Csoi=PuCsoi,
AF?= ? 11510 ? 0.48T (913 ? 1927?K).
The tables of thermodynamic functions for Pu2C3 and PuC2 cannot be compared on account of the ab-
sence of thermal data. However, using the data of [43] on the evaporation of pure plutonium and the thermal
data, cited in [44], we can find the values of A F in the high-temperature region.
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For the process
pviiq --> Pugas (14)
AF?=79570-22.39T cal (1366-1835?K): (15)
AF? = 81360-23.32T cal (2017-2472?K). (16)
From these equations and Eqs. (7) and (8), we find for
Pt]lig+ PUC(sol)
AF-= -13440-2.37' cal (1366-1835?K) (18)
and for
(17)
Piing+ (2- x) Csoi = PuC2-x (sol)
AF -= -4350-6,77 cal (2017--2472?K).
(19)
(20)
To eliminate certain contradictions, the author of [44] proposes that Eq. (20) be changed, and reduces it to
the form
AF= -7580-5.337' cal (1933-2495?K). (21)
There are no data on the thermodynamics of Pu3C2 (the t-phase).
Entropy. It may be assumed that the entropy of PuC0.87 at 0?K is equal to R (0.13 ln 0.13 + 0.87 in
0.87) = 0.77 cal/mole ? deg. This value should be added to that found experimentally (see Table 7), and then
S;98 for PuC0.87 = 18.1 cal/mole .deg, which agrees with the value proposed in [39]. Evidently the thermal
functions of PuC13.3 cited in Table 7 should be recalculated, considering the new value of the entropy, in-
creasing the absolute values of S'T and F?1493/T by 0.77 cal/mole ? deg. Correspondingly, the enthalpy
of formation for PuC0.3, calculated according to the evaporation data, using the third law of thermodynamics,
proves equal to -9.0 kcal/mole.
In the report [39], the following values of the entropy are recommended for Pu2C3 and PuC2: 41.6 ? 3
and 22.5 ? 2 cal/mole .deg, respectively.
LITERATURE CITED
1. E.Westrum, E. Suite, and H. Lonsdale, Advances in Thermophysical Properties at Extreme Tempera-
tures and Pressures, S. Gratch (editor), ASME (1965), p.156.
2. R. Andon et al., Trans. Farad. Soc., 60, 1030 (1964).
3. J. Farr, See [1], p. 162.
4. E. Storms, The Uranium-Carbon and Plutonium-Carbon Systems. Report at the Conference of Ex-
perts,on the Thermodynamics of Uranium and Plutonium Carbides, IAEA, Vienna (September, 1968).
5. E.Westrum, Jr., Notes on the Thermodynamic Properties of Carbides of Actinides (Preliminary
survey). See [4].
6. T. Mukaibo et al., Thermodynamics of Nuclear Materials, IAEA, Vienna (1962), p.645.
7. J. Moser and 0. Kruger, J. Appl. Phys., 38, 3215 (1967).
8. C. Affortit, Personal communication, made by R. Lalleman. See [4].
9. L. Harrington and G. Rowe, Carbides in Nuclear Energy, L. Russel (editor), Vol. 1 (1964), p.342.
10. L. Levinson, ibid., p.429.
11. E. Storms, The Refractory Carbides, Academic Press, New York-London (1967).
12. L. Levinson, J. Chem. Phys., 38, 2105 (1963).
13. A. Macleod and S. Hopkins, Proc. Brit. Ceramic. Soc., 8, 15 (1967).
14. E. Storms and E. Huber, J. Nucl. Mater., 23, 19 (1967).
15. I. Craig, Cited according to [4].
16. W. Robinson and P. Chiofti, Report JS-1061 (1966). Cited according to [4].
17. E. McIver, AERE-R 4983, Harwell (1966). Cited according to [4].
18. I. Piazza and M. Sinnot, J. Chem. Engng. Data, 1, 451 (1962).
19. E. Huber and C. Holley, Cited according to [4].
20. L. Leithaker and T. Godfrey, J. Nucl.Mat., 21, 175 (1967).
21. E. Storms, Thermodynamics, Vol. 1, IAEA, -Vienna (1966), p.309.
22. C. Holley, Letter to the Conference of Experts on the Thermodynamics of Uranium and Plutonium
Carbides (August, 1968).
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23. W. Behl and J.Egan, J.Electrochem. Soc., 113, 376 (1966).
24. E.Huber, E. Head; and C. Holley, J. Phys. Chem., 67, 1730 (1963).
25. P. Rice, R.Bajzhiser, and D. Ragone, Thermodynamics of Nuclear Materials, IAEA, Vienna (1966),
p.331.
26. H. Blank, The Ternary System U-C-N. Some Conclusions on the Behavior of Solid Solutions of UC
-UN. See [4].
27. J. Counsell, R. Dell, and J. Martin, Trans. Farad. Soc., 62, 1736 (1966).
28. E.Westrum and C.Barber, J. Chem. Phys., 45, 635 (1966).
29. E. Speidel and D. Keller, BMJ 1633 (1963). Cited according to [26].
30. L. Harrington, CN-LM-4461 (1963). Cited according to [26].
31. T. Godfrey, J.Wolley, and J. Leitnaker, ORNL-TM-1596 ,(Rev. 1, 1966). Cited according to [26].
32. K. Spear and J. Leitnaker, ORNL-TM-2106 (1968).
33. 0. Kruger and H. Savage, J. Chem. Phys., 40, 3924 (1964).
34. M. Rand, Thermodynamic Evaluation of the Plutonium-Carbon System. See [4].
35. P. Gross, C, Hayman, and H. Clayton, Thermodynamics of Nuclear Materials, IAEA, Vienna (1962),
p.653.
36. W.Hubard, T. J. D. ANL-15554 (1962). Cited according to [26].
37. F. Feder, See [35], p.665.
38. E. Huber and C.Holley, Thermodynamics of Nuclear Materials, IAEA, Vienna (1962), p.581.
39. V. V. Akhachinskii, The Heat and Entropy of Formation of Plutonium Carbides. See [4].
40. F. Harris et al., Cited according to [34].
41. W.Olson and R. Mulford, Thermodynamics of Nuclear Materials, IAEA, Vienna (1968), p.467.
42. G. Campbell, L. Mullins, and J. Leary, ibid., p.75.
43. Mulford, RNL, Thermodynamics, Vol.1, IAEA, Vienna (1966), p.231.
44. M. Rand. Atomic Energy Review, 4, Special Issue 1, IAEA, Vienna (1966), p.7.
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ABSTRACTS
SLOWING DOWN OF RESONANCE NEUTRONS IN MATTER
COMMUNICATION 4
D. A. Kozhevnikov and V. S. Khavkin UDC 621.039.512.4
The time dependence of the neutron age rs(u, t) is examined. In the simplest (Wigner) spectral ap-
proximation, for isotropic scattering and constant mean free path
2h
Ts (U,x-
3
Here r5(u) is the total steady-state neutron age, h the total scattering probability, and x = t/(t(u)), where
(t(u)) is the average slowing-down time.
The analytic features of the complete formal solution of the steady-state slowing-down problem are
studied. The spatial, angular, and energy distributions of neutrons close to the source are obtained in ex-
plicit form. This result does not depend on the order of the BN-approximation (N 1) and has the same
form for all spectral approximations:
(z, u, IA) = X (z, u, (z, u); (2)
(3)
,I, \ c_z2/4To(u) z2
To (z, 0 V4Ivrou) 1+44 [Ts (U)? To (U)1+ ...} (4)
(
The neutron spectrum 4/0(u), the total, age rs(u), the Fermi age r0 (u), and the second spatial-angular moment
rs(u, /1) were calculated previously [1, 2] in four spectral approximations (Wigner, Weinberg?Wigner, and
the generalized and standard Greuling?Goertzel approximations). The quantities rs(u, it) and Z(u, ?) (the
first spatial-angular moment) depend on the angular distribution of the source neutrons. The condition for
the applicability of (3) and (4) is formulated as the inequality
z
2-co (u)
, (5)
^ max
where Amax is the maximum slowing-down length in the interval. If condition (5) is satisfied the classical
age approximation is valid for media with any hydrogen content but is not applicable to an absorbing modera-
tor. The results (3)-(5) are valid for an arbitrary energy dependence of the reaction cross sections and,
as is true of the more general formal solution, are easily generalized to take account of inelastic scattering
and diffraction anisotropy.
At large distances from the source the spatial and energy neutron distributions are determined by
the character of the energy dependence of the total interaction cross section. To explain the principal prop-
erties of the distribution function, determined by the resonance character of the Z(u) dependence, a single
negative resonance (interference minimum) of the cross section is considered in the Wigner approximation
for isotropic scattering.
X (z-I- 0 (u) 4,tr, (u) s u?) T s (a)] + ? . ?} ;
1 {, , zZ
In this case
To (z, (u) F (z),
where the buildup factor B(u) describes the neutron spectrum, and F(z) is independent of energy and is
(6)
Translated from Atomnaya Energiya, Vol. 29, No. 6, p.448, December, 1970. Original article sub-
mitted May 20, 1970.
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? N. Y. 10011. All rights reserved. This article cannot be reproduced for any purpose whatsoever without
permission of the publisher. A copy of this article is available from the publisher for $15.00.
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determined only by the width of the resonance r and the characteristics of the interaction h and at the
resonance energy:
(z/X)2z + 13 11 0
F (z) = xr (0) k x z JJ
(7)
where E1(x) is the exponential integral, X = Em-lin, and ,3 = hIl2t. This same result holds for two and more
negative resonances havingthe same values of Emin. In the latter case 8-+ fl* = 1+ 82 +. . .
LITERATURE CITED
1. D. A. Kozhevnikov and V. S. Khavkin, Atomnaya Energiya, 27, 143 (1969).
2. D. A. Kozhevnikov and V. S. Khavkin, ibid., 29, 365 (1970).
INVESTIGATION OF THE CALIBRATION CHARACTERISTICS
OF A RADIATION THE RMODIVERTER IN HIGH-INTENSITY
FIELDS OF IONIZING RADIATIONS
V. S. Karasev, S. S. Ogorodnik, UDC 621.039.564
and Yu. L. Tsoglin
An integrated heat flux calorimeter, known as a radiation thermodiverter (RTD), has been proposed
for measuring heat generated by radiation; this device features high accuracy, high sensitivity, quick re-
sponse, and arbitrary shape and size.
E, mV
7,0
6,0
5,0
3,0
2,0
1,0
z
0 2,0 4,0 50 50
W, W
Fig. 1. Calibration curves of RTD
(radiation thermodiverter) exposed
to pile radiations of different inten-
sity.
The behavior of the calibration curves of the RTD in re-
sponse to irradiation wei-e studied experimentally in this ar-
ticle, and the results of long-term radiation stability tests di-
rectly in the core of thenuclear reactor are reported.
The experimental procedure is designed to take separate
account of the effects of intensity, integrated fast flux, and y-
radiation. The transport channel in a reflector at the inter-
face with the reactor core, and an experimental channel in a
spent-fuel storage pool, were selected as the exposure zones
in the experiment. An RTD with a cylindrical cavity 20 mm
in diameter, 20 mm in height, 0.30 mV/W sensitivity, was
tested in the reactor channel, and another RTD with an inner
cavity 9 mm in diameter and 12 mm in height, with a sensitivity
of 66.6 mV/W, was tested in the pool channel.
Results of the RTD calibrations at different positions in
the height of the reactor channel, at different stages in the ex-
posure, are plotted in Fig. 1.
The integrated fast (sulfur) flux amounted to 1.2 ? 1019
neutrons/cm2 by the time the experiment was over.
For long-term testing for radiation stability, a thermo-
diverter unit made up of copper?constantan thermopiles with
mica interlayers sandwiched between them as electrical insula-
tion, was placed in a hermetically sealed capsule which was
Translated from Atomnaya Energiya, Vol. 29, No. 6, p.449, December, 1970. Original article sub-
mitted March 26, 1970.
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inserted into a reactor core cell, replacing one fuel element. The capsule was exposed to irradiation rated
at 10 MW for over three months, and received over that time span an integrated fast flux (sulfur) of 4.3 ? 1020
neutrons/cm2, and an integrated thermal flux (gold) of 6.7 ? 1020 neutrons/cm2, with an integrated y-radiation
dose (lead) of 2.7 ? 106 Mrad. A monotonic decline in the dose rate in lead, referred to 1 MW, was observed,
ending up at 4.65% by the end of the exposure, and this was accounted for by a decrease in the intensity of
the soft component of the y-radiation stemming from fuel burnup in neighboring fuel elements in the core.
These experiments demonstrated that the calibration curves of the thermodiverter retain their lin-
earity and stability in high-intensity fields of ionizing radiations. The practical feasibility of long-term
service of the thermodiverter for in-pile measurements was thereby demonstrated.
CALCULATION OF PHOTONEUTRON DISTRIBUTION
BY MONTE CARLO METHOD
A. A. Morozov and A. I. Khisamutdinov UDC 539.125.5.348:546:45
The conditions of the problem are as follows. A pulsed source of y-rays placed at a height h above
the surface of the earth emits 1.667-2.2 MeV photons in a cone of a given angle. The photons fall on beryl-
lium-bearing rock and initiate photonuclear reactions in beryllium, producing neutrons which pass through
the air. The beryllium is assumed to be uniformly spread through the rock.
The quantities investigated are the integrated neutron fluxes in given time and energy intervals at
various distances from the source. The neutron flux depends on the parameters of the beryllium-containing
rock as well as on height, time, energy, and distance from the source.
Plane symmetry in the neutron part of the problem and the uniformity of time were used in finding the
required integrated fluxes by a specially developed modification of the Monte Carlo method. Local flux
calculations were thus avoided. In the process of solving the problem the neutron trajectory was displaced
to the proper point in phase space and then the corresponding "importance of production" was calculated at
the point of actual production.
Time histograms were obtained and interpreted for beryllium-bearing granite with porosities of 0,
3, and 6%, energy intervals of 0-0.4 and 0.4-400 eV, heights h of 20, 45, and 100 m, and distances from the
source r of 0 and 10 m. The time axis of the histograms contains the time intervals 10-5-10-3; 10-3-5 ? 10-3;
5 ? 10-3-10-2; 10-2-5 ? 10-2; and 5- 10-2-10-1 sec.
The results of the calculations confirm the possibility of air prospecting for beryllium from a height
of 45-60 m with a y-source 5. 1012 photons/sec for a beryllium density of ?10-5 g/cm3, and can contribute
to the choice of optimum instrument characteristics.
Translated from Atomnaya Energiya, Vol.29, No. 6, pp. 449-450, December, 1970. Original article
submitted November 11, 1969; revision submitted February 26, 1970; abstract submitted June 23, 1970.
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PRECISION SYSTEM FOR THE DETERMINATION OF
OXYGEN BY FAST NEUTRON ACTIVATION
I. P. Lisovskii and L. A, Smakhtin* UDC 621.039.564
A Method for determining oxygen from the reaction 016(n, p)Ii16 is suggested. The samples are ir-
radiated in stainless steel ampoules in an NG-160 neutron generator which is provided with a device for
interrupting the deuteron beam (diameter of the ampoules 15 mm, length 20 mm, and internal volume 1.6
cm3). The maximum flux at the point of irradiation amounts to 5 ? 108 neutrons/cm2 ? sec. The integral
neutron flux through the internal volume of an ampoule (sample) is directly proportional to the flux through
the ampoule walls. This makes it possible to use the induced activity of the ampoule (reaction Fe56(n, p)
?
Mn) as the flux monitor. The sample position during the irradiation need not be exactly determined.
The y-emission of the samples and of standards was measured with a detector (NaI(T1) crystal with a
size of 150 mm x 100 mm and with a hole of 20 mm diameter and 50 mm depth) and an LP4050 512-channel
analyzer.
The N16 activity was measured in the range 4,8 to 8 MeV. Lucite (C5H802) Was used as an oxygen
standard. The ampoules were transported in an automated pneumatic Shuttle. The irradiation time was
30 sec, the delay time 0.9 sec, and the exposure time 30 sec. The background generated by the ampoule
was taken into account. The accuracy of the determinations amounted to 1-2.5 relative percent, depending
upon the oxygen concentration. The sensitivity was 10-4g 02.
VVR REACTOR SEMIAUTOMATIC 'ACTIVATION
ANALYSIS SYSTEM
I. P. Lisovskii, L. A. Sinakhtin, UDC 621.039.56
N. V. Filippova, and V.I. Volgint
A semiautomatic pneumatic shuttle system for a nuclear reactor is described. The specimens were
irradiated in hermetically sealed polyethylene capsules which were placed in the shuttle rabbit. After ten
rabbits with specimens have been placed in the loader, all further operations (irradiation exposure, extrac-
tion of capsule with specimen from the rabbit and delivery of specimen to the laboratory for measurements)
are handled automatically. The total time elapsed from the end of the irradiation exposure to the beginning of
measurements is 10 to 20 sec (depending on the size of the capsules).
Work done in activation analysis with the aid of this semiautomatic shuttle and irradiation system is
reviewed. Operating experience with this pneumatic shuttle, over a four-year period, has demonstrated
the versatility, reliability, and ease of operation of the system.
*Translated from Atomnaya Energiya, Vol. 29, No. 6, p. 450, December, 1970. Original article submitted
March 20, 1970.
tTranslated from Atornnaya Pnergiya, Vol. 29, No. 6, p.450, December, 1970. Original article submitted
March 20, 1970.
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METHOD OF ATTENUATING RADIAL BETATRON
OSCILLATIONS IN CYCLIC ACCELERATORS
L. A. Roginskii and G. F. Senatorov UDC 621.384.6.07
Systems for the attenuation of betatron oscillations are of great importance for the development and
use of cyclic accelerators designed for high intensities and energies. The conventional attenuation systems
[1-4] comprise pickup electrodes, which measure the deviation of the beam from the chamber axis (sensors),
and electrostatic deflectors (correctors), which adjust the transverse momentum of the particles. The
present article is a theoretical consideration of an attenuation method slightly different from the conven-
tional method. The principle of the present method, which was suggested by the author of the article and
by Yu. S. Ivanov in the Radiotechnical Institute of the Academy of Sciences USSR, is based on the fact that
the voltage of several accelerating sections is modulated by a signal proportional to the signal of a sensor
measuring the beam shift. The momentum change which is induced in the particle's momentum by the
modulation of the longitudinal accelerating field causes a shifting of the particles in radial direction. The
system parameters can be selected so that the radial force attenuates the betatron oscillations.
Compared with the conventional methods, the present method is characterized by the advantage that
the existing accelerating sections can be used as correctors (without affecting their actual purpose); thus,
special deflectors, which would occupy additional space, are unnecessary. The relatively low efficiency is
the principal disadvantage of the method. The low efficiency results from the fact that the indirect effect
upon the radial motion (by modifications of the longitudinal momentum) is small. Nevertheless, one can
accomplish in such a system a constant attenuation which is equal to several ten revolutions, and this suf-
fices for suppressing certain transverse beam instabilities (e.g., drag instabilities).
The article describes in detail one of the versions of the proposed attenuation system consisting of
a sensor and two accelerating sections used as correctors. The voltage of the first section (first section,
as far as the motion of the particles is concerned) is modulated with a signal which is proportional to the
sensor signal. Therefore, after passage through the resonator, the particles which arrive in the equilib-
rium phase acquire a momentum different from the equilibriurn momentum. A radial force proportional
to the relative momentum deviation caused by the modulation of the accelerating voltage acts upon the par-
ticles. The phase of the voltage applied to the second resonator is opposite to the modulation of the first
resonator, and therefore, the momentum deviation of the particles vanishes after the passage of the part-
tidies through the resonator, and the particle motion is not affected by a radial force.
The system was described with a matrix method. The attenuation decrement and the stability regions
were determined. It could be shown that the distance between the sensor and the first section must be equal
to an integer of the wavelength of the betatron oscillations in order to obtain the highest efficiency; the
distance between the sections must be equal to a half integer, of the betatron oscillation wavelength.
LITERATURE CITED
1. C. Pruett, Fifth International Conference on High Energy Accelerators, Frascati (1965), p.363.
2. J. Martin, Fifth International Conference on High Energy Accelerators, Frascati (1965), p.347.
3. H. Barton, A Summary of the Cosmotron Experiments on the Coherent Vertical Instability, MOB-7
(November 27, 1963).
4. P.R. Zenkevich, Thesis, Moscow (1965).
Translated from Atomnaya Energiya, Vol. 29, No. 6, pp. 450-451, December, 1970. Original article
submitted November 20, 1969; abstract submitted June 17, 1970; revision submitted June 17, 1970.
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PERMANENT ELECTROMAGNET WITH BUILT-IN
RADIOISOTOPE THERMOELECTRIC DIRECT CONVERTER
A. Kh. Cherkasskii and V. S. Makarov UDC 621.362
An independently functioning electromagnet with a built-in thermoelectric direct converter for direct
conversion of the heat energy of radioactive decay into electrical energy, and combining the positive fea-
tures of a permanent magnet (continuous and independent operation without the aid of external power sup-
plies) with the advantages of an electromagnet (high field strength, high flux density, linearity of B?H
characteristics, stability to effects exerted by strong externally applied magnetic fields, capability of ser-
vice at temperatures well above the Curie point of ferromagnetic materials), is proposed by the authors
and examined.
This nquasipermanent" magnet (see Fig. 1) consists of the thermopiles 1 and 2 placed on the surface
of the fuel slug 3 and the electrically closed winding 4, which envelops the ferromagnetic core 5. A part of
the core is cut off to form a working gap. The fuel slug consists of several capsules with radioactive iso-
tope 6 placed within a current-conducting casing 7. The heat energy of radioactive decay is converted by
the thermoelectric cells into electrical energy, so that a short-circuit current appears in the magnet wind-
ing, and a magnetic field is established in the working gap.
The current in question depends on the parameter Y acr/x, of the thermoelectric material, which is
expressed in A/W units:
q0b1Fe y A
(1-km -HT) '
where a, cr, are the thermal emf, electrical conductivity, and thermal conductivity of the thermoelectric
cell; qo is the density of the heat flux flowing through the thermoelectric cell; biFe is the heat contact sur-
face; m is the ratio of the winding resistance to the resistance of the pn pair; zT is the Ioffe criterion.
When the number of turns 'opt = [(1 + zT)/mJ1/2 has been optimized, the field intensity in the working gap
will be
(1)
4011Fe
Ho YA/m;
2km0 "1/1+zTlo
and the magnetic flux density in the working gap will be:
f1040b/Fe
B6? y ml,
2km0 1/1-1- zT /o
Fig. 1. Layout of perma-
nent electromagnet.
(2)
(3)
while the volume density of electromagnetic energy in the working gap will
be;
w6_ H8B8 7 [ knzo v?
q07Fezno i/m3, (4)
2
and the specific electromagnetic energy referred to the weight of the core
will be:
WFe= 1
H oBaS Fele. r qobY
TS
Fe17e1Fe 4 L kmoV 1+ zT-I2 16 j17Fe
(5)
where mo = m/co2; /o, So are the length and area of the working gap; 1Fe,
SFe, YFe are the length, cross-sectional area, and specific weight of the
core; ?0 is the magnetic permeability constant; k is a multiplicative factor
characterizing the contribution made by the core resistance to the total
circuit resistance.
Calculations for basic parameters of this autonomous electromagnet
made from thermopiles of silicon?germanium alloy for various types of
Translated from Atomnaya Energiya, Vol. 29, No. 6, pp. 451-452, December, 1970. Original article
submitted March 3, 1970.
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radioactive fuel, including: Sr" pu238, cm244 , u232, ce144, pozio,
, and Th228, are cited. It is shown that other
types of built-in director converters can be used along with the thermoelectric converter, e.g., thermionic
converters or thermophotoelectric converters.
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LETTERS TO THE EDITOR
EXPERIMENTAL STUDY OF THE CHARACTERISTICS
OF THE IR-100 RESEARCH REACTOR
L. V. Konstantinov, I. N. Martem'yanov,
V. A. Nikolaev, A. A. Sarkisov,
V. F. Sachkov, A. V. Sobolev,
S. V. Chernyaev, and I. S. Chesnokov
UDC 621.039.521:621.039.55
The water-cooled, water-moderated IR-100 teaching and research reactor was commissioned in 1967;
it was designed for a thermal power of 100 kW and used uranium dioxide (10% enriched) as nuclear fuel.
Sheathless fuel cassettes were used for the first time in the IR-100, in conjunction with small graphite dis-
placers and a demountable graphite reflector; these enabled a variety of critical-composition configurations
to be created.
The release of heat from the active zone of the reactor is effected by the natural directional circula-
tion of water. The water is cooled in a heat exchanger built into the vessel of the reactor. In order to im-
prove the natural circulation of the water, the reactor vessel contains a concentric cylindrical barrier sit-
uated below the active zone. The barrier separates the active zone and the space above it filled with hot
water from the water cooled in the heat exchanger.
Thermal column
Fig. 1. Schematic chart indicating the loading
of the active zone and the arrangement of the
experimental sections in the IR-100 reactor:
1) ionization-chamber channels; 2) vertical
experimental channels (VEC); 3) graphite re-
flector; 4,5) graphite displacers; 6) fuel cas-
sette; 7) photoneutron source; 8) shuttle chan-
nel; a) automatic-control rods; b,c,d) scram
rods; e,f) manual-control rods; g) CEC; h1-h3
HEC.
A description of the construction of the IR-100 and
its rated physical and technological parameters was given
earlier [1, 2].
In this paper we shall present the results of some
measurements carried out during the introductory pe-
riod and the subsequent running of the reactor, charac-
terizing its experimental potentialities.
A schematic chart representing the loading of the
active zone and the arrangement of the experimental
sections of the reactor are presented in Fig. 1. The
working load (charge) of the active zone comprises 43
fuel cassettes (2.4 kg U235), 40 graphite displacers, and
one beryllium photoneutron source.
The reactivity reserve of the reactor with the ex-
perimental sections empty is 0.58%. The total com-
pensating capacity of the control rods is 4.7%.
The reactivity introduced by the mobile can [1] is
0.06% on filling it with graphite and 0.05% on filling it
with water. Filling the central experimental channel
(CEC) with water increases the reactivity of the reactor
by 0.48%. Filling the other experimental regions with
water has no effect on the reactivity of the system.
Table 1 presents the thermal-neutron fluxes and
the dose rate of y-radiation in the vertical experimental
Translated from Atomnaya Energiya, Vol.29, No. 6, pp. 453-454, December, 1970. Original article
submitted January 23, 1970.
o 1971 Consultants Bureau, a division of Plenum Publishing Corporation, 227 West 17th Street, New York,
N. Y. 10011. All rights reserved. This article cannot be reproduced for any purpose whatsoever without
permission of the publisher. A copy of this article is available from the publisher for $15.00.
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TABLE 1. Thermal-Neutron Fluxes and
Dose Rate of y-Radiation in the Experi-
mental Systems
Experimental sys-
tem
Thermal- neutron
flux, ? 1012 neu-
trons/cm2 ? sec
Dose rate of y-
radiation, ? 106
R/h
Experimental sys-
tem
Thermal- neutron
flux, ? 1012 neu-
trons/cm2. sec
Dose rate of y-
radiation, 106
R/h
CEC
2,75
22
VEC- 5
0,99
1,9
VEC-1
1,12
2,1
VEC-6
0,97
1,9
VEC-2
1,11
2,2
VEC-7
0,3
0,71
VEC-3
0,34
0,72
VEC-8
0,22
0,70
VEC-4
0,24
0,68
Can
0,1
0,36
TABLE 2. Characteristics of the Horizon-
tal Experimental Channels
I Thermal-
Dose rate of
Experimental neutron flux,
r-radiation,
system neutrons/cm2
R/h
..sec
Fast-neutron
flux, neu-
trons/cm2
? sec
HEC-1 (h1)
HEC-2 (h2)
HEC- 3(h3)
6,8.105
5,5.105
7,7-105
1,43.105
2,53.107
1,54.105
2,86.107
1,65.107
3,52.10'
channels (VEC) and on the front wall of the unloaded "draw-
bridge" can at the level of the center of the active zone,
referred to the nominal reactor power of 100 kW.
The thermal-neutron fluxes were determined by
reference to the absolute activity of a set of gold indica-
tors, using the method of (R, y)-coincidences (maximum error 7%). The dose rate of y-radiation was mea-
sured with small-scale 'y-chambers (maximum error 20%).
Table 2 gives the thermal and fast-neutron fluxes and the dose rate of y-radiation at the exit from the
horizontal experimental channels (HEC) for the case of open gates (valves), measured with a universal ra-
diometer of the RUS-7 type and referred to the nominal reactor power of 100 kW.
Practical experience showed that the cooling system employed in the IR-100 reactor had a consider-
able reserve factor, enabling the reactor power to be raised to between 200 and 300 kW without seriously
changing the loading of the active zone.
LITERATURE CITED
1. Yu. M. Bulkin et al., Atomnaya E'nergiya, 21, 363 (1966).
2. Yu. M. Bulkin et al., Byull. Izobret., No. .15, 184 (1968).
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EFFECT OF THE FLOW VELOCITY OF A VAPOR ? LIQUID
MIXTURE OF COOLANT, AND OF VAPOR CONTENT, ON
SURFACE HEAT-TRANSFER COEFFICIENT IN BOILING
OF WATER INSIDE TUBES
F. F. Bogdanov
UDC 621.039.534.44
The literature contains surprisingly little data on the effect of steam content and the flow velocity of
a coolant vapor?liquid mixture on surface heat-transfer coefficients in the case of boiling in channels and
tubes. This appears to stem from the fact that many investigators have failed to detect any such effects in
their experiments at all. One of the reasons for this wciuld be insufficient attention on the part of investi-
gators to keeping the heating surface sufficiently, clean. Experience has shown that the presence of a 0.02-
0.03 mm thick oxide film on the heating surface will result in an appreciably steep rise in thermal resis-
tanceoverthe path of the heat flux in boiling, offsetting any comparable drop in steam content or in the flow-
speed of the vapor?liquid mixture. Hence, only those investigators who stage their experiments on suf-
ficiently clean heating surfaces will have any success in defecting the influence exerted by the above fac-
tors on surface heat transfer when water is boiled in channels.
Generalizations about boiling heat transfer within tubes consequently either fail to take account of
the effect of vapor content and of the flowspeed of the vapor?liquid coolant mixture at all, or else take ac-
count of the effect of vapor content alone, and that in at best a highly approximate manner.
These circumstances render it more convenient to seek out some new form for making generaliza-
tions on experimental data, one which would take into account the effect on surface heat-transfer coeffi-
cients of changes in the relative steam content by weight, and in the flowspeed of the vapor?liquid coolant
mixture.
At the basis of these generalizations, we placed our improved formula from reference [1], with ther-
modynamic similitude criteria brought into the picture, and proposed for the purpose of determining the
surface heat-transfer coefficients in boiling of water on clean heating surfaces when steam content is either
positive or negative, as well as the recommendations in reference [2] on treating the effect exerted on heat-
transfer coefficients in boiling of a liquid phase in tubes where the flowspeed of the liquid phase is linear,
and laminar flow goes over into turbulent flow.
a? 10-4, kcal/m2 h. deg
20
10
8
7
6
5
111,11111E2111
1111M=MINIIIIME
MEMINMEMEIMMIMITIIMIMMR
Mrailtilli.111.111=1111.1111111
11111.1111.11111
RiIIi*?U III
4 5 6 7 8.910? 2 3 4 5 6 7 8'
W mx, m/sec
Fig. 1. Dependence of surface heat-transfer coef-
ficients for boiling in tubes on flowspeed of vapor
?liquid mixture; 0) author's data for boiling in
slightly oxidized tubes (pressure p = 55 atm, heat
flux q = 2.6 ? 105 kcal/1112.h, liquid-phase flow-
speed wo = 0.4 m/sec); Q) same, at p = 125 atm,
q = 4 ? 105 kcal/x/12.h, wo = 0.35 m/sec; same,
for p= 140 atm, q = 3.7 ? 105 kcal/m2.h, wc, = 0.4
m/sec; *) data borrowed from reference [1], for
boiling of water in tubes (p = 170 atm, q = 2 ? 105
kcal/m2.h, w = 1245 kg/m2. sec); (11) same for
q = 4.5 .105 kcal/m2.h; II) same, for q = 6 ? 105
kcal/m2.h; c) same, at q = 8 ? 105 kcal/m2.h.
Translated from Atomnaya Energiya, Vol. 29, No. 6, pp. 454-456, December, 1970. Original article
submitted June 3, 1969; revision submitted November 13, 1969.
o 1971 Consultants Bureau, a division of Plenum Publishing Corporation, 227 West 17th Street, New York,
N. 1'. 10011. All rights reserved. This article cannot be reproduced for any purpose whatsoever without
permission of the publisher. A copy of this article is available from the publisher for $15.00.
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a ? 10- 3 kcal/m2? h ? de
200
150
100
50
1
i_....-
...---?
..--
--- -
i
I
,
' ,....9.?61
0 ???
I
...
...? ""
.."
i0
i
...???? ...?
Si"...
./
........?"'4????
0
_i
I
I 15
..,
f..?
2
?
...-----
411*
1
e - ? ,
-..-
....
??
i
e
jiff
toff 4
..
-
o
...0 e
- :-...-_::::_
4,
_
....._. ... ... ... _......2...,......... .
..,:..,,,_
-x 05 04( 43 02 01 0 01 0,2 , 03 -,?x
Fig. 2. Dependence of the surface heat-transfer coefficients on the total
effect exerted by vapor void content and vapor-liquid mixture flowspeed:
)5) data borrowed from reference [1] for a vapor-liquid mixture at p
= 170 atm and q = 2 ? 105 kcal/m2?h; e) same, at q = 4.5 ? 105 kcal/m2?h;
P) same, at q = 6 ? 105 kcal/m2?h; 4) same, at q = 8- 105 kcal/m2.h.
Curves 1, 2, 3, 4 are theoretical curves plotted on the basis of formula
(3) for q values of 2 ? 105, 4.5 ? 105, 6 ? 105, and 8 ? 105 kcal/m2.h, respec-
tively; curves 5, 6, 7, 8 are curves plotted on the basis of the formula
recommended by the authors of reference [1] for the same heat fluxes,
respectively; curves 9, 10, 11, 12 are curves plotted on the basis of
formula (3), for p = 100 atm-and the same respective heat fluxes; curves
13-16 are plotted on the basis of formula (4), for p = 170 atm and the
same respective heat fluxes; curve 17 is plotted on the same basis, but
for concentric slit orifices, at q = 1.2 .106 kcal/m2.h.
Experimental data borrowed from references [1, 3], and taken from our own experiments, were used
in processing the experimental results; 1) on surface heat transfer when subcooled water is boiled on the
practically clean heating surfaces of narrow annular channels, and obtained at very high heat flux levels
[q = 106 to 3.106 kcal/T/12.h] and at pressure p = 175 atm; 2) on surface heat transfer in the case of boiling
in oxide-coated tubes, and obtained at pressures of 50, 120, and 140 atm.
The experiments were carried out by a procedure described in the literature [2], but the arrangement
was modified slightly.
A tube of 1K1118N9T steel with an outer diameter of 23.5 mm and wall thickness of 1.25 mm, total
length 1 = 3290 comprising two sections tobe heated: /1 = 345 mm, and /2 = 1020 mm, and with a stabilized
section left unheated, of length lo = 805 mm, was used as the working section in the experiments.
Four Chromel-Alumel thermocouples 0.2 mm in diameter were used on each of two cross sections
on the /2 interval of tubing, and four thermocouples were used in one cross section on the 11 interval. The
thermocouples measured the temperature of the external surface of the experimental tube; the temperature
of the tube inner surface was determined by calculations based on K. D. Voskresenskii's formula.*
The experiments were carried out under rigorously stationary conditions. Only the heat load on the
economizer lengths of tubing was varied before each series of experiments. As a rule, the maximum heat
load was established in the first experiments in each series, and was found to decrease from one experi-
ment to the next. Whenthe heat load on the economizer tube lengths remained unaltered, five to six experi-
ments each lasting 30 min were carried out.
*This formula was derived by K. D. Voskresenskii upon the present author's request back in 1949, but has
unfortunately remained unpublished. The formuliandi2Sidias 71577. C,
At ? ql u
w 2nX/ [k ? 4,1 )
di d1 Ohj
where qh accounts for heat losses to the surroundings.
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The steam content by weight of the coolant varied only insignificantly (by a few percent), making it
possible to discern the effect exerted by the flowspeed of the vapor?liquid mixture on the surface heat-
transfer coefficients, independently of the vapor content, since the direct effect exerted by the vapor phase
on the heat-transfer process remains practically unaffected. At the same time, the vapor content by volume
varied appreciably from one experiment to the next, and the flowspeed of the vapor?liquid mixture also
underwent appreciable changes.
Data from these experiments are plotted in Fig. 1 in the form of the dependence a = f(w ). The ex-
perimental data points plot out with a modest spread (relative to the skewed straight lines giving the slope
n = 0.16 at all the heat fluxes and pressures measured). This means that the change in heat flux and pres-
sure over the range investigated will have no effect on the way heat transfer accompanying boiling of water
in tubes is affected by the flowspeed of the vapor?liquid mixture. But the diagram also shows experimental
data from reference [1] on heat transfer when water boils in tubes. A correction intended to eliminate any
direct effect of the vapor content by weight was introduced into the values of the surface heat-transfer co-
efficients in this case. The experimental data from [1] corrected in this manner fit with very little spread
about the skewed straight lines representing the slopes n = 0.16. Accordingly, the effect of the flowspeed
of the vapor?liquid coolant mixture on the surface heat-transfer coefficients in boiling in tubes and chan-
nels can be taken into account by means of the power-law multiplier w??16 at those parameters, or by the
simplex (wmx/wcr)" in generalized formulas, at any pressures of the vapor?liquid coolant mixture.
This dimensionless criterion links the rate of surface heat transfer, in boiling in channels, with the hydro-
dynamics of two-phase flow. When we also take into account the recommendations put forth in reference
[1] on handling the effect cxerted on heat transfer by the steam content by weight in boiling, the total effect
of the flowspeed of the vapor?liquid coolant mixture and of the vapor content by weight in this mixture on
heat transfer when the coolant boils in the channels in forced flow, can be treated properly by using the
dimensionless complex:
x0 4 wmx) 0.16
(1.1Cr
The magnitude of the component of the surface heat-transfer coefficient ascribed to boiling can be
determined with sufficient accuracy by using the formula
, Tcr Ts T)2/3
C (PPC: )?.12( ? 0:1 7
? s
kcal
m2 ? h ? deg'
(1)
(2)
Hence, the convective component will be determined from Eq. (2) multiplied by the complex (1). The
total heat-transfer coefficient in boiling in tubes is given by the formula
.
c "2 ( Ts )2/3 q" [i+x 0, Wmx) 41?4 kcal
Pi Tcr ?Ts I wcr I J mz ? h ? deg.
(3)
Figure 2 shows experimental data from reference [11 on heat transfer in boiling of water in tubes and
when the vapor content is positive, as approximated by formula (3). The free proportionality factor in this
formula was adopted in accordance with our recommendations for a weakly oxidized surface, with the as-
signed value 0.8. The broken curves on this graph are averaging curves [1] plotted for the corresponding
heat flux levels.
The theoretical curves based on formula (3) describe the experimental data in [1] quite closely, and
almost coincide with the averaging curves based on those data. Figure 3 also shows the theoretical curves
based on formula (3) for the pressure p = 100 atm. It is clear from the diagram that these curves are equi-
distant from the theoretical curves plotted for p = 170 atm.
Here we also have the experimental data from [1] relating the same heat flux levels at negative vapor
content (subcooled liquid), at the pressure 170 atm. The experimental data are approximated by the theo-
retical curves plotted on the basis of a formula in which the multiplicative factor taking the convective com-
ponent into account is raised to the negative power recommended by the authors of reference [1]. In that
case, the computational formula becomes
T8 \ 2/3
\Pt ) Tcr ?Ts ) 0.7 [1+ x WInx) 0.18]-2'8
wcr /
The coefficient C is assigned the value 0.8 in this case.
kcal
rn2 ? h ? deg.
(4)
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It is clear from the diagram that the experimental data in reference [1] referring to the case of nega-
tive vapor void content are described quite closely by formula (4). Our experimental data on surface heat
transfer in boiling of subcooled water at the pressure p = 170 atm on a practically clean heating surface
of annular channels ,with forced flow (indicated by circles blackened in top half), also plotted in that dia-
gram, are again approximated closely by formula (4). The free proportionality factor is assigned the val-
ues of 1 and 2 in that case, depending on how clean the heating surface is. These experimentally derived
data points fit the approximating curve with a very small spread.
LITERATURE CITED
1. N. V. Tarasova, A.A.Armand, and A.S.Kontkov, in: Heat Transfer at High Heat Flux Levels, and
Other Special Conditions [in Russian], A. A. Armand (editor), Gosenergoizdat, Moscow (1959), p.6.
2. F. F. Bogdanov, Izv. Akad. Nauk SSSR, Otd. Tekh. Nauk, No. 4, 136 (1955).
3. W. Elrod et al., Trans. ASME, 89, No.3 (1967).
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NEUTRON YIELD FROM THICK TARGETS BOMBARDED
WITH 11.5 AND 23.5 MeV PROTONS
V. K. Daruga and E. S. Matusevich UDC 621.384.633
The measurements were performed at the FI cyclotron. The energy of the proton beam was deter-
mined by the range in aluminum foils and by a semiconductor detector. At the time of the measurements
the energy was 11.5 ? 0.5 MeV (molecular hydrogen) and 23.5 ? 0.7 MeV (atomic hydrogen).
The targets of Li, Be, C, Mg, Al, Ti, Fe, Co, Ni, Cu, Zn, Nb, Cd, Ta, W, Pb, Bi, and U had their
natural isotopic compositions, and thicknesses equal to the range of the bombarding protons.
The experimental procedure and technique were described earlier [1].
Absolute measurements were made with a BF3 long counter. The angular distributions of neutrons
from the targets were measured with a ZnS(Ag) scintillator in Plexiglas and a B10 + ZnS(Ag) scintillator
with a polyethylene neutron moderator 5 cm thick. Backgrounds were determined with a shadow cone. The
total yields were obtained by integrating the areas under the angular distribution curves, taking account of
the neutron spectra and the detector characteristics. The shape of the angular distribution in the 0 > 140?
region was obtained by extrapolation. The angular distributions for all targets except carb9n fall smoothly
from Slab = 0 to Blab = 180?. The neutron yield from carbon increases in both the forward and backward
directions.
Table 1 shows the absolute neutron yields in 4r and in the tab = 0? direction. Table 2 gives the
characteristics of the neutron spectra in the range En = 1-6 MeV for E. = 23.5 MeV, listigg values of the
parameters Tw and TL for describing the spectra in the form ?Enexp(?En/Tw) and ^,41/11exp(?En/TL)
respectively. The spectra of neutrons emitted in the ?lab = 0? direction from light targets (Li, Be, C) are
very different from spectra of evaporated neutrons. All spectra have different values of T in the ranges
En < 3 MeV and 3 < En < 6 MeV. The data on neutron spectra for Ep = 11.5 MeV are given in [2].
TABLE 1. Absolute Neutron Yields from Thick Targets
Target
EP = 11.5 MeV
E =23? 5 MeV
P
Y (0?), neutrons/sr ? AC Y4ir, neutrons/pCi
Y (0?), neutrons/sr ??Ci I Y47, neutrons/pCi
Li
Be
Mg
Al
6,3?109?10%
1,75?107?6%
1,7.108?10%
?
3,9.10194-15%
1,1.108?27%
6,1.108?17%
1,35.109+18,5%
9,5.108?13%
2,2.1010+10%
1,3?108?9%
1,0-109?8%
1,5.109+8%
5,5?1019?16%
1,1.1011+14%
8,0.108?25%
7,5.109+15%
1,15.1010?13%
Ti
4,8.109?23%
3,95.109?10%
3,6.1019+14%
Fe
?
2,8-109?10%
2,5.1018?16%
Co
5,0.1094-16%
4,35.109+10%
3,7.1018?14%
Ni
4,6.108?18%
1,35.109+8%
1,0 1018?16%
Cu
?
4,1.109+8%
3,9?1018?15%
Zn
2,6-108+23%
3,3.109?11%
3,0.1019?17%
Nb
4,1?108?7%
4,6-109+15%
5,0.109?8%
5,0.1010?12%
Cd
3,7.109+19%
5,0.109+8%
5,2?1018?14%
Ta
1,2.109+16%
3,95.109+10%
5,0.1018?14%
9,5-107?10%
.
1,05.109?19%
?
?
Pb
5,0.107?10%
?
2,95.109?11%
3,5?1019?18%
Bi
5,6-108?18%
?
?
7,4?107?7%
9,0.108+17%
5,7.109+11%
7,0?1010?14%
Translated from Atomnaya Energiya, Vol.29, No. 6, pp. 456-458, December, 1970. Original article
submitted June 30, 1970.
C5 1971 Consultants Bureau, a division of Plenum Publishing Corporation, 227 West 17th Street, New York,
N. Y. 10011. All rights reserved. This article cannot be reproduced for any purpose whatsoever without
permission of the publisher. A copy of this article:is available from the publisher for $15.00.
1233
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5
4
3
2
3
2
us
0
is
9:It
?
o
0 0
4iif
,t. Ati
c
+
E A
0 n
?1
A
n
A
.
10 20 30 40 50 60. 70 80 90 Z
Fig. 1. Ratio of neutron yields Y(00)/Y(900)
from thick targets bombarded with protons.
a) Ep= 11.5 MeV, mean square error IS
= 5-10%; b) Ep= 23.5 MeV, 1(5 = 10-15%;
0) En > 0; II) En > 1.6 MeV; A) En > 1.8
MeV; +) En 8 MeV from [3].
TABLE 2. Parameters for the Analytic Description of
Spectra
Target
0 = 0?
0= 90?
Tw, MeV
TL, MeV
Tw, MeV
TL, MeV
Li
Be
Al
Cu
Cd
Pb
0,7--1,2
0,9-2,3
1,0-2,7
0,95--1,55
0,85--1,15
0,85--1,1
1,0-1,27
0,8-1,4
1,1-2,9
1,2-3,9
1,2-1,8
'1,0-1,3
1,1-1,25
1,25-1,45
0,7-1,0
0,80-2,1
0,9-2,2
0 8-1,2
0,75-1,1
0,8-0,9
0,95-1,25
0,8-1,1
0,95-2,6
1,1-2,6
0,95-1,4
0,95-1,25
1,0-1,1
1,25 --1,4
Figure 1 shows the ratio of the yields Y(0?)/Y(90?) as a function of the Z of the target nuclei.
The authors thank V. A. Dulin and N. N. Pal,chikov for help with the measurements, and A. A. Ognev
for measuring the proton energy.
1. V. K. Daruga et
2. V. K. Daruga et
Moscow (1970).
3. B. Cohen, Phys
1234
LITERATURE CITED
al., Preprint FI [in Russian] (1970).
al., Bulletin of the Nuclear Data Information Center [in Russian], No.6, Atomizdat,
.Rev., 98,49 (1955).
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Declassified and Approved For Release 2013/04/09: CIA-RDP10-02196R000700060001-1
A METHOD OF DETERMINING THE IRON CONTENT
OF CORROSION PRODUCT DEPOSITS
B. A. Alekseev, N. N. Kozhenkov, UDC 621.039.553.36
and G. A. Kotel'nikov
The current method of analyzing the amount of accumulated corrosion product deposits in nuclear
reactor circuits, using specimens of zirconium alloys, is based on boiling the deposits in 6N HCI. How-
ever, solution is very slow and systematic errors may be incurred owing to incomplete solution of these
products (chiefly iron oxides). These difficulties can be eliminated by determining the content of the cor-
rosion product deposits from their y-radiation.
Study of the deposits was performed on specimens from outside the active zone ? in the heat-transfer
agent of the forced-circulation loop of the MR reactor of the I. V. Kurchatov Institute of Atomic Energy.
The specimens were prepared from zirconium alloys. The spectrum of the y-quanta, measured by means
of a Ge(Li) detector, clearly displayed Co6? and Cr51 isotopes. The iron content was determined by means
of o-phenanthroline. The error of the iron determination was assessed by the accuracy of the spectro-
photometric method. Thus, during the experiment we determined how the activity of Co6? in the sweeping-
out liquor depends on its iron content.
Analysis of the experimental data revealed that in the corrosion product deposits, the activity of Co6?
is proportional to the iron content to within ?10% (see Table 1). This fact may be used for rapid and re-
mote-controlled determinations of accumulated iron concentration of specimens, and also in pipelines (for
studying the kinetics of sweeping away of deposits), and other similar problems.
We thank V. F. Kozlova for helping with the assembly of the spectrometer, V. A. Ermakov for his use-
ful advice, and V. F. Leonov for operating the apparatus.
TABLE 1. Activity of Co6? versus Concentration of Accumulated Iron
Fe, mg/liter
(.103)
11
12
18
19
22
27
29
32 I34
42
44
54
57
58
69
Co60; counts
/sec
4,0
6,5
8,5
8,0
10,0
12,0
13,0
10,5
14,5
19,0
16,5
21,0
17,0
23,0
27,0
Translated from Atomnaya Energiya, Vol. 29, No. 6, p.458, December, 1970. Original article sub-
mitted July 17, 1969; revision submitted June 1, 1970.
O 1971 Consultants Bureau, a division of Plenum Publishing Corporation, 227 West 17th Street, New York,
N. Y. 10011. All rights reserved. This article cannot be reproduced for any purpose whatsoever without
permission of the publisher. A copy of this article is available from the publisher for $15.00.
1235
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Declassified and Approved For Release 2013/04/09: CIA-RDP10-02196R000700060001-1
GROUP SEPARATION OF FISSION PRODUCTS BY
THE CHROMATOGRAPHIC METHOD
L. N. Moskvin and N. N. Kalinin
UDC 543.544.6
Analysis of radioactive elements in the water of the reactor primary loop is protracted and compli-
cated, no matter whether the methods of analysis used are sedimentation techniques, extractive techniques,
or chromatographic techniques [1-3]. The appearance of Ge(Li)-detectors in 7-ray spectroscopy has made
the job of identifying radioactive elements a much simpler one. It has become possible to estimate the con-
tent of individual isotopes directly from the 7-ray spectrum of the primary loop water in the reactor sys-
tem [4]. But because of the different yields in fission, different activation cross sections for impurities,
and peculiar spectral features, some of the radioactive isotopes may escape detection directly against the
7-ray spectrum background of the total sum of active products present in the coolant stream.
1500
1000
500
L
20 40 60 80 100 120 140 160
Channel number
1131
285
1131
365
180
200 220
Fig. 1. 7-Ray spectrum of fraction sepa-
rated out on column packed with AB-17
anion-exchange resin.
500
400
300
200
100
-
cz?
oo:
210
40 60 80 11117 120 140
Channel number
150
Fig. 2. 7-Ray spectrum of fraction separated out on
column with di-2-ethylhexylphosphoric acid.
Translated from Atomnaya Energiya, Vol. 29, No. 6, pp.458-461, December, 1970. Original article
submitted January 4, 1970; revision submitted April 2, 1970.
1236
0 1971 Consultants Bureau, a division of Plenum Publishing Corporation, 227 West 17th Street, New York,
N. Y. 10011. All rights reserved. This article cannot be reproduced for any ,purpose whatsoever without
permission of the publisher. A copy of this article is available from the publisher for $15.00.
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Declassified and Approved For Release 2013/04/09: CIA-RDP10-02196R000700060001-1
C5137
661
CSI34
605
o cs134
o 570
cs134
797
?i
10 I? 30 .50 70 .90 1 111 1_?
0 I )0 , 150 170 1-kji' 210 1230 250 270 j 2901
20 40 60 80 100 120 140 160 180 200 220 240 260 280 300
Channel number
Fig. 3. y-Ray spectrum of fraction separated out on
third column in first two free volumes of eluate.
The authors of the present article made some attempts to combine group express chromatographic
separation of fission products with subsequent identification on a Ge(Li)-spectrometer, an approach which
makes provisions for singling out the most highly active impurities in the reactor loop water (viz., iodine
and alkali metals) and considering them in separate groups.
Radioactive elements have to be stabilized in a single chemical form in order to isolate them in
quantitative work. The introduction of formic acid is important in setting up conditions favorable to chro-
matographic separation of fission fragments. As a strong reducing agent, formic acid contributes to the
conversion of different forms of iodine and bromine to a single reduced form, 1- or Br-, which then makes
it possible to isolate these elements quantitatively on a column with a strongly basic anion-exchange resin
(AB-17 in our case) in the formate form. The acidity of the solution needed in order to separate out the
rare earths from the alkali and alkali earth metal on a chromatographic partition column of Teflon coated
with di-2-ethylhexylorthophosphoric acid as the stationary organic phase is achieved at the same time, and
with ease.
A system of columns made of glass, all of the same dimensions (100 mm in height, 12.5 mm in diam-
eter) and connected in series, was utilized in the chromatographic separation. The first column was filled
with AB-17 anion-exchange resin with grain sizes from 100 to 250 it, in the formate form (HCO2-). The sec-
ond column consisted of Teflon in pellet form, coated with di-2-ethylhexylorthophosphoric acid. The prepa-
ration of this type of column has been described in detail in the literature [51. The third column was filled
with Dowex-50X8cation-exchange resin, grain sizes 100 to 250 IA, in the 11+ _form. Cation-exchange resin
KU-2 lends itself equally well to this application.
The aqueous solution to be analyzed (100 to 250 ml in volume), containing traces of iodine, cesium,
barium, lanthanum, and cerium, was acidified to pH = 2 with formic acid, and was passed under pressure,
at a flowspeed of 8 to 10 ml/min, through the array of columns. The eluate was collected in a receptacle
and checked for activity. All the activity contained in the solution under analysis was retained in the sys-
tem of columns after the solution had made one traversal of the system.
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152 5014,9
La140
487
Baf40
C6e 436qajLtL La14
00 815
60140
536
[II I I I I
20 40 60 80 100 120 140 160 180 . 200 220 240 260 280 300
Channel number
Fig. 4. y-Ray spectrum of fraction separated out on
third column.
The columns, together with the vessel for the original working solution, were washed with 10 to 20
ml 0.01 M solution of formic acid. No activity was detected in the wash effluent. The coating and washing
operations take 15 to 20 min. After washing, the system was analyzed. The third column was washed with
10 ml 6 N hydrochloric acid (1.5 to 2 free volumes). Each column and the test tube with the eluate from the
third column were covered with stoppers and measured on a y-ray spectrometer with a 512-channel ana-
lyzer.
As was to be expected, quantitative absorption of iodine takes place in the first column: the y-ray
spectrum (Fig. 1) indicates the presence of the isotope 1131. No other elements were detected in the first
column. The y-ray spectrum of the second column (Fig. 2) is indicative of the presence of isotopes Ce141
and Ce144, i.e., absorption of rare earths is observed in the second column. No isotopes of other elements
were detected. The isotope La14? is lacking, since the measurements were taken 19 days after the chemical
separation had been effected. Isotopes Cs137 and Cs134 (see Fig. 3) were detected in the eluate from the third
column. Ba140 and its daughter La14? remained in the column (Fig. 4). The extent to which the separation of
each group of elements in the respective fraction went to completion is confirmed by the absence of activity
in the filtrate taken from the system of columns, and by the absence of mutual contamination of the distinct
fractions.
The scheme of ex?press chromatographic groupwise separation of fission products contained in the
reactor loop waters, with subsequent identification of the isotope composition on a semiconductor 'y-ray
spectrometer as described, is thus proposed as a regular technique.
The authors take this opportunity to express their deep thanks to Yu. E. Loginov for having made it
possible to use the Ge(Li)-y-ray spectrometer for the measurements, and for the assistance which
he kindly rendered in the work.
LITERATURE CITED
1. Radiochemical Studies of Fission Products, Vol.I-III, New York (1951).
2. Radiochemical Analysis of Fission Products [in Russian], Yu. M. Tolmachev (editor),
Izd-vo AN SSSR, Leningrad (1960).
1238
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Declassified and Approved For Release 2013/04/09: CIA-RDP10-02196R000700060001-1
3. Yu. P. Saikov, Atomnaya Energiya, 20, 123 (1966).
4. 0. A. Miller et al., Atomnaya Energiya, 25, 524 (1968).
5. B.K.Preobrazhenskii et al., Radiokhimiya, 10, 377 (1968).
1239
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Declassified and Approved For Release 2013/04/09: CIA-RDP10-02196R000700060001-1
EXPERIMENTAL VERIFICATION OF THE RADIATION-CHEMICAL
METHOD FOR PRODUCING TETRACHLOROALKANES
A. A. Beer, P. A. Zagorets,
V. F. Inozemtsev, L. A. Maiorov,
V. I. Slavyanov, G. A. Artyushov,
I. F. Srrygaev, and V. A. Novozhilov
UDC 541.15
A pilot plant designed to produce new products, tetrachloroalkanes, by radiation-chemical methods
was put on stream in late 1967 at the Grozny chemical combine. At the present time, the experimental op-
erations have been pretty much completed, and current plans envisage expanding the facility to full indus-
trial scale.
The tetrachloroalkanes are of great interest to the chemical processing industry, as semifinished
products useful in the synthesis of polymeric materials, additives, lubricants, pesticides, stabilizers,
plasticizers, etc., [1]. Tetrachloropropane and tetrachloropentane are acquiring special importance.
The tetrachloroalkanes are obtained by a reaction of telomerization from ethylene and carbon tetra-
chloride:
CC14
C H4
C2H4
Water
out
//
,,H4
T_D:1
Water in
Reaction
product On the basis of their research findings, the present au-
thors designed and built a pilot plant with two divisions, one
for telomerization, the other for rectification, of the tetra-
chloroalkanes. The basic layout of the telomerization division
is shown in Fig. 1.
Carbon tetrachloride is supplied by the pump to the ab-
sorber tower 1 for absorption of unreacted ethylene. The solu-
tion enters the reactor 2, into which compressed ethylene is
bubbled. The sources (total activity ?18 kg-equivalents radi-
um) are raised up from their storage pool into the central ir-
radiator tube of the reactor under pressure from compressed
nitrogen [7]. The irradiated mixture from the reactor is then
throttled to 3-5 atm in the separator 3. The unreacted ethylene
from the separator is directed to the absorber tower 1, where
it is dissolved in carbon tetrachloride and recycled to the pro-
cess. Liquid reaction products leaving the separator 3 are
throttled to atmospheric pressure in the separator 4, and pass
4
x?C2H4+CC14=C1(CH2CH2)5CC13.
This reaction is usually initiated by free radicals obtained via
thermal decomposition of peroxides or azo-compounds. It has
been shown [2-4] that this reaction is initiated by -y-emission
from Con, and the radiation method of initiation has certain ad-
vantages here. Subsequently, the radiation-chemical process
has been described in the literature by other investigators as
well [5, 6].
Nitrogen in
Fig. 1. Basic layout and flowsheet of
facility designed for radiation telomeri-
zation between CC14 and C2H4 (reaction
unit).
Translated from Atomnaya Energiya, Vol. 29, No. 6, pp. 461-463, December, 1970. Original article
submitted June 10, 1970.
1240
0 1971 Consultants Bureau, a division of Plenum Publishing Corporation, 227 West 17th Street, New York,
N. Y. 10011. All rights reserved. This article cannot be reproduced for any purpose whatsoever without
permission of the publisher. A copy of this article is available from the publisher for $15.00.
Declassified and Approved For Release 2013/04/09: CIA-RDP10-02196R000700060001-1
Declassified and Approved For Release 2013/04/09: CIA-RDP10-02196R000700060001-1
50 from there to the rectification step so that the unreacted
carbon tetrachloride can be driven off (and recycled to
? the process), and the pure tetrachloroalkanes can be iso-
40 late&
30
`,.`1
20
10
- I
30 20 10
0 10 20 30 40 50
Distance, cm
Fig.2. Dose field of reactor (accord-
ing to data provided by ferrosulfate
dosimeters): IP) location of dosimetric
capsule; x) dose rate.
All of the process equipment was made of Kh18N1OT
steel. The absorber tower was packed with porcelain rings.
The reactor, 550 liters in volume and 800 mm in diameter,
was equipped with a coil for heating or cooling, and a bubbler
for feeding the ethylene stream.
The process is carried out at 15-20 atm and 100?C, for
6 h, and the resulting reaction mixture contains ?80%unreacted
carbon tetrachloride and approximately equal quantities of
tetrachloropropane and tetrachloropentane. The impurity con-
tent remains the same, to within a fraction of apercent.
The assigned process parameters correspond to the
molar composition of the irradiated mixture R = [CC141/[C2H41
= 5 ? 10. Any change in this composition will mean a change
in the content of the distinct tetrachloroalkanes in the mixture,
as described by the equations
C IR C 2R
? Fi2 ?= (C -F 1) F (C IR+ 1) (C 2R + 1) '
C3R
F3? (CIR+ 1) (CO +1) (C3R +1) etc'
where Fi is the molar fraction of the telomer in the mixture; R is the molar ratio [CC10[C2H41; Ci is the
transfer constant.
The transfer constants, according to the data collected by the present authors, have the following
values:
Temperature,
?C
0
20
50
100
140
Cl
C3
0.045
3
10
0.059
2.9
9
0.89
2.8
7
0.155
2.7
5
0.218
2.6
4.7
A drop in the reaction temperature will depress the content of tetrachloroalkanes in the reaction mix-
ture slightly, since the energy of activation of the reaction is 5.5 kcal/mole.
Dosimetric monitoring of the reactor (with the aid of a methylene blue solution) showed the average
absorbed dose rate to be 10 rad/sec. The dose field in the interior of the reaction, taken from readings of
ferrosulfate dosimeters, is given by the curve plotted in Fig. 2.
The radiation-chemical yield (converted to the dose rate 1 rad/sec) is 22,000 to 27,000 molecules of
tetrachloroalkanes per 100 eV of radiation absorbed. According to laboratory data, the yield is inversely
proportional to the dose rate, with the exponent 0.73, and is equal to 30,000 molecules per 100 eV at a dose
rate of 1 rad/sec.
The radiation efficiency is 0.23, which is below the rating (0.38).
The formula
P =3.7.10-9Mavg' (0)0.27 (Vp)o.no
where P is the reactor throughput, in kg/h; g' is the radiation-chemical yield at a dose rate of 1 rad/sec,
May is the average molecular weight of the tetrachloroalkanes, 17 is the radiation efficiency; A is the source
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activity [gram-equivalents radium]; V is the reactor effective volume [liters]; p is the specific weight of
the irradiated mixtures [g/cm3], was proposed for large-scale simulation of the process, and was checked
for experimental verification.
The experimental verification revealed that the process takes place in a stable manner, responds
amenably to control measures, and ceases immediately after the sources are removed from the reactor
core. A slight induction period was discovered. The process parameters and the composition of the re-
sulting mixture were found to be in close agreement with laboratory data.
The discharge coefficient of the carbon tetrachloride at the telomerization step is 0.8 to 0.9 (the
theoretically predicted discharge coefficient is 0.78). Ethylene losses are negligible.
The tetrachloroalkanes obtained after rectification exhibit the required degree of purity.
This flowsheet is a reliable one, but could be improved. The process equipment should be made of
titanium, since stainless steel is still subject to corrosive attack.
Optimization calculations were performed, on the basis of prevailing prices, with due attention
to the basic features of the process, on reactor dimensions and activity of radiation sources for different
levels of productivity. It was found economically feasible to utilize a reactor of fairly large volume with
low-level irradiators. For example, the optimum reactor volume for a throughput of 200 kg/h was found to
be ?5 m3, with the activity of the sources set at 55 to 60 kg-equivalents radium.
Engineering cost calculations showed that the net cost of tetrachloroalkanes in full-scale industrial
production is 600 to 700 rubles/ton. Compared to the process achieved with azo-bis-isobutyronitrile, the
radiation-chemical method requires much less initiator (the amount required is cut by 10 to 20 times).
LITERATURE CITED
1. R. Kh. Freidlina and Sh. A. Karapetyan, Telomerization and New Synthetic Materials [in Russian],
Izd-vo AN SSSR, Moscow (1961).
2. M. A. Besprozvannyi, A. A. Beer, and G. B, Ovakimyan, Inventors' Certificate No. 106988, Byull . Izobret.,
No.14 (1957).
3. A. A. Beer et al? in; Radioactive Isotopes and Nuclear Radiations in the National Economy of the USSR
[in Russian], Gostoptekhizdat, Moscow (1961), p.211.
4. A. A. Beer et al., Neftekhimiya, 2, 617 (1962).
5. C. David and P. Gosselian, Tetrahedron, 18, 369 (1962).
6. M. Takehisa, M. Yasumoto, and J. Hosaka, Kogyo Kagaku Zasshi, 65, 531 (1962); ibid., 66, 259 (1963).
7. V. A. Dobrovol'skii, B. I. Ryabov, and Yu. V. Kastrup, Inventors' Certificate No. 166975, Byull. Izobret.,
No.24 (1961).
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Declassified and Approved For Release 2013/04/09: CIA-RDP10-02196R000700060001-1
USE OF XENON PROPORTIONAL COUNTER ESCAPE
PEAKS FOR X-RAY RADIOMETRIC ANALYSIS OF
TUNGSTEN IN ORES
N. G. Bolotova, V. V. Kotel'nikov, UDC 550.835
and E.P, Leman
The use of proportional counters significantly expands the technical capabilities of x-ray radiometric
ore analysis and increases the number of elements which can be determined by this method. For example,
the high accuracy and sensitivity of x-ray radiometric analysis in the determination of elements with atomic
numbers Z 30 by means of the characteristic radiation of the K series can only be achieved with the help
of proportional counters [1]. An increase in dimensions and an increase in filling-gas pressure to atmo-
spheric makes it possible to increase the efficiency of xenon proportional counters to the extent that ele-
ments with a Z of 40-55 are determined from the K series with satisfactory accuracy and sensitivity [2, 3].
For elements with Z > 60, the analysis can be made on the basis of the characteristic radiations of the L
series [4] since the detection efficiency for 60-100 keV photons is very small in proportional counters. Use
of the K series of these elements for proportional counter analysis is only possible in practice by recording
the escape peaks [5].
The escape peaks of xenon counters are of particular interest in the determination of heavy elements
(with Z 70) in ores, and particularly tungsten. Tungsten determination by means of the L series is
complicated by the fact that it is close in energy (8.5 keV) to the K lines of iron (6.5 keV), copper (8.0 keV),
and zinc (8.6 keV), which are often present in ores along with the tungsten, and the counter resolution in
1200
? 800
1-4
400
20 40 50 80 8, keV 0 5 IOW 03,%
Fig. 1. Example of the use of escape peaks in an SRPO-12 xenon propor-
tional counter for determination of tungsten content in ores by means of
the K-series characteristic x-ray radiation (Co57 source); a) secondary
y-spectra obtained from simulated samples with varying content of tung-
sten trioxide; 1) 0; 2) 0.5%; 3) 1%; 4) 2.5%; 5) 5%; 6) 10%; b) dependence
of spectral ratios on tungsten trioxide content in simulated samples.
Translated from Atoxnnaya Energiya, Vol.29, No 6, pp. 463-465, December, 1970. Original article
submitted May 14, 1970.
o 1971 Consultants Bureau, a division of Plenum Publishing Corporation, 227 West 17th Street, New York,
N. Y. 10011. All rights reserved. This article cannot be reproduced for any purpose whatsoever without
permission of the publisher. A copy of this article is available from the publisher for $15.00.
1243
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Declassified and Approved For Release 2013/04/09: CIA-RDP10-02196R000700060001-1
this energy region, which is 18-20%, is insufficient for complete separation. The tungsten K lines (57-59
keV) efficiently excite the characteristic radiation of the xenon filling in a proportional counter. The xenon
is practically transparent to its own characteristic x radiation, and the radiation consequently leaves the
counter or is absorbed in the counter walls producing clearly defined escape peaks. The intensity of an
escape peak is determined by the photon flux in the characteristic K radiation from tungsten and the posi-
tion of the peak in the secondary spectrum ?the energy difference between the K radiations of xenon and
tungsten (see Fig. la).
An SRPO-12 xenon proportional counter was used as the detector. The characteristic tungsten x
radiation was excited with a Co57 source (123 keV). Measurements were made with an AI-8 spectrometer
on simulated samples of tungsten ores (a mixture of quartz sand and gypsum was used as filler) over a large
solid angle without collimation of the radiation. A maximum was observed in the 60 keV region of the sec-
ondary instrumental spectra which resulted from the superposition of the tungsten K lines (57-59 keV) and
the xenon K-series escape peak for singly scattered radiation (-90 keV) from the Co57 source. This situa-
tion, along with the low detection efficiency for photons with energies above 50 keV, prevents the use of
xenon counters for the determination of tungsten in ores by means of the characteristic K radiation.
A different picture was observed in the spectral region 20-40 keV where one finds the xenon escape
peaks associated with the tungsten K series. Three peaks were very clearly distinguished: the first (in the
25 keV region) corresponds to the energy difference between the tungsten Ka lines and the xenon Ki3 lines;
the second (in the 29 keV region) is equal to the difference between the energies of the xenon and tungsten
K a lines; the third (with energies of 37-38 keV) results from the difference between the energies of the
Kig line of tungsten and the Ka line of xenon. The intensity of the escape peaks increases with an increase
in tungsten concentration. The most intense peak is the second one, which can be used as an analytic line
for spectral ratio techniques..
Figure lb gives the curve for the dependence of spectral ratios on tungsten trioxide content in simu-
lated samples. Scattered radiation at 46 keV was chosen as the internal standard for background. The
spectral ratios n were normalized to the value no in the ore-free sample. The n/no curve is close to linear
in the tungsten trioxide concentration range 0-5%. The sensitivity of the analysis can be increased by using
collimation of the radiation and by reducing the scattered radiation background in the region of the escape
peaks. Thus x-ray radiometric analysis of some heavy elements, and of tungsten in particular, by means
of characteristic K-series x radiation can be performed with the help of the escape peaks from xenon pro-
portional counters when direct recording of the K radiations of these elements proves to be impossible or
inefficient. Such a method can be used for the determination of tungsten in tungsten and molybdenum?tung-
sten ores. In the analysis of antimony?tungsten or tin?tungsten ores, the use of this technique is compli-
cated by the fact that the xenon escape peaks resulting from the presence of tungsten coincide in energy
with the analytic K lines of antimony and tin.
LITERATURE CITED
1. R.I. Plotnikov et al., Instruments and Methods in X-Ray Analysis [in Russian], No.2, Izd.SKBRA,
Leningrad (1967), p.126.
2. E. P. Leman et al., Development of Geology and Mine-Survey Services in Nonferrous Metallurgical
Enterprises (Mining Industry Series) [in Russian], Izd. TsNIItsvetmetinformatsiya, Moscow (1970),
p.31.
3. A. L. Yakubovich, E. I. Zaitsev, and S. M. Przhiyalgovskii, Nuclear Physics Methods for the Analysis
of Minerals [in Russian], Atomizdat, Moscow (1969).
4. I. V. Tomskii, V. N. Mitov, et al., Instruments and Methods in X-Ray Analysis [in Russian], No. 5, Izd.
SKBRA, Leningrad (1969), p.111.
5. R. I. Plotnikov et al., Instruments and Methods in X-Ray Analysis [in Russian], No.2, Izd. SKBRA,
Leingrad (1967), p.121.
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Declassified and Approved For Release 2013/04/09: CIA-RDP10-02196R000700060001-1
DIAGNOSTICS OF AN ELECTRON ? ION BUNCH
USING BREMSSTRAHLUNG
M. L. Iovnovich, V. P. Sarantsev, UDC 533.95:621.039.61
and M. M. Fiks
A new method has been proposed [1] for the collective acceleration of ions. The method is based on
the possibility of creating electron?ion bunches which are accelerated as a unit in external electromagnetic
fields. The creaction of a bunch begins with the formation in an external magnetic field of a thin ring of
relativistic electrons (major radius of the ring is R, minor radius is a) where storage of ionized atoms oc-
curs. The storage process has been discussed [2-4]. During storage, bremsstrahlung from the electrons
arises through electron collisions with atoms and ions, and this bremsstrahlung can be used for bunch
diagnostics.
The bremsstrahlung from a relativistic electron in an atomic nucleus is essentially anisotropic. For
y ? 1 (y is the electron relativistic factor in the bunch at rest), almost all the radiation is concentrated in
a small solid angle Q = 47r sin2(0/2), where 9/2 = 1/y is the angle between the photon direction of propagation
and the tangent to the trajectory at the point of radiation [5].
The average number N of photons with energies e = hv/mc2 eo emitted by the ring per unit time into
an angle A, within which the "illuminated" portion of the radiation detector is seen, is determined by the
expression
zo
4rt
dN = E dc,,D (Zo, e') cbQ E nzozieR
dt
Zo z=o
E0
(lc sin2 (1)
\ where (I)(Zo, c) is the cross section for emission of photons with energies in
\
\
\ the range c, e + dc from a nucleus of charge Zo, nzoz is the concentration of
>. heavy particles (Zo is the nuclear charge and Z is the ionic charge), and je is
the electron current density in the ring.
Fig. 1. Diagram of the ar-
rangement of the brems-
strahlung detector D.
G(a/2, y
0,02
0,01
;7-00
0 0,02 0,04
50
30
20=
405 cx/2, rad
Fig. 2. Ratio of bremsstrahlung in-
tensity incident on the detector to
the total intensity from the entire
ring.
Translated from Atomnaya Energiya, Vol. 29, No. 6, pp. 465-467, December, 1970. Original article
submitted January 4, 1970.
0 1971 Consultants Bureau, a division of Plenum Publishing Corporation, 227 West 17th Street, New York,
N. Y. 10011. All rights reserved. This article cannot be reproduced for any purpose whatsoever without
permission of the publisher. A copy of this article is available from the publisher for $15.00.
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10
0 1 2 3 t.105, sec
Fig. 3. Number of photons with
energies 0.1 :sh, s 1.0 MeV
incident on the detector in an in-
terval At = 10-5 sec: ) stor-
age from atomic beam; ----)
storage from residual gas; ne
= 1014 cm-3, a = 0.1 cm, Ne
=1014, a/2 = 0.02.
where
Integration is carried out over the ring cross section Q = ra2.
Equation (1) was obtained under the assumption the electron current
was transparent to photons.
If the detector dimension d ?a and the electron and heavy par-
ticle concentrations are constant over the cross section Q of the
ring, then
Zo
dN 2 ? A
'Alec 1
(16'0 (Zo, e') E n,oz _ y2 cop sin. ,
?
zo CO Z=0
(la)
where Ne is the total number of electrons in the ring.
The function A(co) and the equations which determine the limits
of integration over yo are found from simple geometric considerations
(see Fig. 1). In the case where not only 1/y ? 1 but also a/2 ? 1,
< 1, one can obtain an approximate evaluation of the geometric fac-
tor G(a/2, 3, y) = (2/7r)y2 f cico sin2(21/4) in analytic form:
( (3 a a 1
3n k 2 T>7;
1 3n (a)2 (32 1 a) 72 2 2 ?
'V
The family of curves G((Y/2, y) I y=const is shown
Fig 2
tan /3=2.5 tan (a/2)
, .
During storage of a single type of ion of a monatomic gas, the
radiation intensity and the number of photons incident on the detector
)
in
(2)
in a time t are given by
dV (d,V p a o
P,
\
N (I) = dN ) 0 G oc 13' Y) P(t),
(d dN t ) 0 Neena deo (zo,
CO
(3)
(4)
(5)
is the radiation intensity of the entire bunch at the initial time t = 0; na is the neutral atom concentration
zo
near the bunch, and the functions s(t) = E nZ0Z/na and p(t) = s(t')dt' are defined in [4].
z=o 0
Small values of e make the main contribution to the integral in Eq. (5). For reason of computational
convenience, we therefore use an expression for cI)(Zo, e) which is valid for the case of small energies
(complete screening) [5]:
4Z,I 1 C)2 2 ( g /q 1
(Zo, = 137 8 1[1.?,(i. -- ln (183Z(T (1 ---- 6 ') ,
where re = e2/mc2 is the classical radius of the electron. Equation (6) is applicable for photon energies
up to the value emax 72/137 + y. Following integration, we obtain
dN 44 4 e e ?en e2-4
k 717 / 0 = ITT/ Neenciq {[-3? 183Z1131/9] [ln + 2y2 in 183Z(71/3}
eo
(6)
(7)
The limits of integration, e0 and e are determined by the spectral sensitivity of the detector. The
number of photons detected during the time of storage depends on the spectral sensitivity of the detector
and the detection efficiency. For bunch diagnostics, one can use a germanium?lithium detector, for which
the maximum spectral sensitivity is in the photon energy range 0.1-1.0 MeV, and the detection efficiency is
a few tens of percent with an energy resolution of ?2%. The frequency of electron synchrotron radiation,
which forms the background in these measurements, is many orders of magnitude less than that of the,ra-
diation detected. By measuring the radiation intensity, one can determine the total concentration of heavy
particles in the ring with an accuracy of a few percent.
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Figure 3 shows the number of photons in the energy range mentioned reaching the detector during
storage of xenon (Zo = 54) (broken down into intervals At = 10-5 sec). This data indicates that one can study
the process of xenon storage in bunches having electron numbers Ne 3. 1012.
The study of ions formed from diatomic gases, particularly protons, requires special consideration.
Nevertheless, one can assume that in a bunch with Ne = 1014, the observation of proton storage is feasible
if the concentration of hydrogen molecules in the region of the bunch is roughly two orders of magnitude
greater than the concentration of residual gas molecules.
We note in conclusion that the proposed diagnostic technique also allows one to determine the total
number of electrons in a ring since the initial concentration of heavy particles is known.
The authors thank A. B. Kuznetsov, Yu. Ts. Oganesyan, and N. V. Rubin for discussions of the problems
involved.
LITERATURE CITED
1. V. I. Veksler et al., Atomnaya Energiya, 24, 317 (1968).
2. M. L. Iovnovich, N. B. Rubin, and V. P. Sarantsev, JINR Preprint, P9-4257, Dubna (1969).
3. Symposium on Electron Ring Accelerators, UCRL-18103, Berkeley (1968).
4. M. L. Iovnovich and M. M. Fiks, this issue p. 1199.
5. Experimental Nuclear Physics [Russian translation], E. Segre (editor), Vol. 1, Izd-vo IL, Moscow
(1955).
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EXCITATION OF RADIAL BETATRON OSCILLATIONS BY
A LONGITUDINAL ACCELERATING FIELD
Yu. S. Ivanov, A. A. Kuzimin, UDC 621.384.6
and G. F. Senatorov
In the adjustment and use of proton synchrotrons it is essential to be in possession of adequate in-
formation regarding the frequency of the betatron oscillations during the whole cycle of acceleration.
Usually at the beginning of the cycle one encounters intrinsic coherent oscillations of the center of
gravity of the beam of accelerated protons, due to the nonzero initial conditions prevailing on injection;
however, the period of their "coherence," which is mainly determined by the distribution function of the
particles in the beam with respect to the betatron-oscillation frequencies, is not very long. For example,
in the case of the 70 GeV accelerator of the Institute of High-Energy Physics, under normal operating con-
ditions the period of coherence is no longer than 3 to 5 ?sec.
In order to measure the frequencies of the betatron oscillations throughout the whole acceleration
cycle, the oscillations must first be excited [1].
In this paper we shall consider one of the methods of exciting coherent radial betatron oscillations.
The method is of the resonance type; however, in contrast to the method described earlier [2], the periodic
stimulating force varies the longitudinal rather than the transverse momentum of the center of gravity of
the beam.
It is well known [3] that the radial betatron oscillations of a particle with a momentum differing from
the equilibrium value are described by the equation
30f0
d2x Sp
dt2 +Q2w2x ---=(?2r?-"-p
Fig. 1. Arrangement for the excitation and observation of betatron oscillations: 1)
pulse initiating the excitation; 2) control system; 3) frequency divider; 4) key; 5) mod-
ulating voltage; 6) accelerating stage; 7) signal electrodes; 8) ring; 9) resonator; 10)
differential amplifier; 11) low-frequency filter; 12) oscilloscope.
(1)
Translated from Atomnaya Energiya, Vol. 29, No. 6, pp.467-469, December, 1970. Original article
submitted December 17, 1969.
1248
C 1971 Consultants Bureau, a division of Plenum Publishing Corporation, 227 West 17th Street, New York,
N. Y. 10011. All rights reserved. This article cannot be reproduced for any purpose whatsoever without
permission of the publisher. A copy of this article is available from the publisher for $15.00.
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where x is the radial deviation of the particle from the equilibrium value; co is the frequency of revolution;
t is the time; Q is the frequency of the betatron oscillations; Sp is the deviation of the longitudinal momentum
from equilibrium; p is the total momentum of the particle; and ro is the average radius of the accelerator.
If the voltage on one of the accelerating stages is modulated in accordance with a law of the f(t) type,
then
N-1
d2x Po
d 14 + Q2?32z r?6)2 p (t) H (t ? 0), (2)
n=0
where Apo is the maximum possible difference of the momentum from equilibrium; H is a unitary function;
To is the period of rotation of the particle; and N is the number of turns.
Let us consider simply the forced solution of (2):
t N-1
x= avotiplpQ E f (t) H (t ?tzto) sin Qco (t ?T) dr. (3)
b
If f(t) = sin qcot (where q is an arbitrary number), then expression (3) takes the form
N-1
oroApo/pQ y, sin q (onto sin Qw (t ?T) dt, (4)
n=0
or finally
N ?
x= r5APOMPQ2 [2 '>-1, sin annq ?-t- ens Q15 E [sin 2.rin (q Q) + sin 2an (q ? Q)] + sin QO E .2:7oz (q ? Q)? cos 2.Toz (q Q)]) , (5)
n-'70 n=0 n=0
where ,51= wt.
When
Q q =
(where m = 0, ?1, ?2, . . . ), solution (5) assumes the resonance form.
The most interesting case is that in which m is the closest whole number to the frequency of the
betatron oscillations Q. This corresponds to the lowest modulation frequency, and it constitutes an important
factor, since the accelerating stages are quite narrow-banded
Qr
(the band width of the accelerating stages in the Institute's
9,84 synchrotron is of the order of 80 to 100 kc/sec).
9,8 I.
-
9,76
.9 6
2 4 16 8 ;0
/5
20
9,72
30 t, msec
Fig. 2. Time dependence of the beta-
tron-oscillation frequency.
? The frequencies of the phase oscillations differ con-
siderably from the frequencies qw, and the mutual influence
of the radial and phase oscillations may be neglected [2]. In
order to confirm the theoretical results we carried out some
experiments on the excitation of radial oscillations in the In-
stitute's proton synchrotron.
Fig. 3. Oscillograms of the build-up of radial and vertical betatron oscillations:
a) sweep 200 psec/cm; b) sweep 70 ?sec/cm.
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A block diagram of the arrangements for exciting and observing the betatron oscillations is presented
in Fig. 1. The voltage frorn a master generator with a frequency of 30fo (f0 being the frequency of rotation of
the particles) is fed to a frequency divider, which divides this frequency by a whole number n (n may vary
in unit steps from 67 to 300). The signal at a frequency of 30f0/n is amplified, passes through a timer-con-
trolled key, and is applied to the grid of the output tube of the accelerating stage, as a result of which the
amplitude of the accelerating voltage is modulated.
The measuring system is also controlled by a timer and contains low-frequency filters considerably
increasing its sensitivity.
An oscillograph incorporating a memory enables information relating to the betatron oscillations to
be analyzed directly from the screen; alternatively, the processes may be photographed and analyzed later.
Our experiments enabled us to measure the frequency of the radial betatron oscillations and also to
establish the relationship between the radial and vertical oscillations at individual points of the cycle up
to energies of the order of 2 GeV. For energies greater than 2 GeV the betatron oscillations of the beam
could not be increased to amplitudes sufficient to allow accurate measurement (-0.5 mm) using only one
accelerating stage.
Figure 2 shows the experimental time dependence of the betatron-oscillation frequency in the acceler-
ating cycle. This relationship may be varied by adjusting the accelerator.
Figures 3a and b present photographs of two oscillograms obtained when studying the development of
betatron oscillations. The upper oscillograph beam represents the excitation of the radial oscillations and
the lower beam represents that of the vertical oscillations arising from the coupling between the radial and
vertical oscillations of the beam. The processes give the appearance of passing through resonance, and in
Fig. 3b (corresponding to a faster sweep) we see how the energy is transferred from one form of oscilla-
tion to the other.
These results demonstrate the efficiency of the proposed method of exciting radial betatron oscilla-
tions at low energies. The use of this method requires no special excitation apparatus and hence demands .
no space for locating such apparatus in the accelerator ring.
In conclusion, the authors wish to thank V. E. Pisarevskii, A. M. Gudkov, and V. P.Ustinov for help in
the experiments.
LITERATURE CITED
1. V. A.Uvarov and G. F. Senatorov, Pribory i Tekh.Eksperim., No.6, 20 (1968).
2. A. A. Kolomenskii and A. N. Lebedev, Theory of Cyclical Accelerators [in Russian], Fizmatgiz, Mos-
cow (1962).
3. A. Shoch, Theory of Linear and Nonlinear Perturbations of Betatron Oscillations in Alternating-Gra-
dient Synchrotrons, CERN, Geneva (1958).
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NEWS
LIEGE MAY 1970 INTERNATIONAL SYMPOSIUM ON
MODERN ELECTRIC POWER GENERATING STATIONS
P. A. Andreev
An international symposium on modern electric power generating stations was held in Liege (Belgium)
in May 1970, and attracted over 500 specialists from 22 countries. A total of 52 papers was presented at
this symposium, dealing the design, fabrication, investigation, adjustment, and operation of heat process
equipment and electromechanical equipment for modern electric power stations. Topics covered in the
papers ranged over: nuclear-fueled electric power stations, gas turbine plants and gas turbines, hydroelec-
tric power stations, and electric power generating stations burning fossil fuels.
Attention was centered on nuclear power at this symposium; topics focused upon were equipment and
operating experience, in relation to nuclear power stations based on different types of reactors, with a large
number of papers taking up these questions and provoking a lively discussion. Equally close attention was
given to the urgent problems of reliability and efficient use of the basic power equipment in modern nuclear
power stations with water-cooled reactors and above all water-moderated water-cooled reactors (reactors,
steam generators, steam turbines, and circulating pumps). The outlook for nuclear power development and
forecasts projecting into the future of nuclear power were discussed to a lesser extent.
Awareness of the damage suffered by the thermal shielding in reactors similar in design to the
American Westinghouse Corp. reactors (e.g., the damage to the SENA Franco?Belgian power station re-
actor) lent added interest to a report on experience in the adjustment and startup of the Obrigheim (West
Germany) power station.
The first full-scale tests of an unloaded reactor to probe into temperature and fluid dynamic condi-
tions brought on severe vibrations in the thermal shielding because of the impact of the stream of water.
These vibrations resulted in severe damage to the surfaces of the reactor pressure vessel, on which the
thermal shielding, 28 tons in weight, rested freely. After trying out several variants in fastening the shield-
ing structures which failed to pay off, even after over 1500 h of testing, a reliable design was worked out
which was checked out again after fuel had been loaded in. A special feature of this successful design vari-
ant is seen in the six support brackets with welded-on retaining vertical backup plates to which the thermal
shielding is pinned. This mode of fastening allows free radial and axial temperature expansion of the
shielding while holding it rigidly fast against any rotational displacements.
Another source of malfunction and misalignment in the performance of the power station was the ex-
cessively high moisture content of the steam feed to the turbine, as a result of the unsuccessful design of
the first and second stages of the steam separator. Attempts to cope with this led to working out a new de-
sign of the separator first stage on full-scale models, with a horizontal cyclone, and using thin moisture
traps manufactured by the Peerless firm as the second separator stage. The separation system thereafter
brought about a moisture content of not more than 0.25% in the steam under the entire range of operating
conditions of the nuclear power station.
Because of the excessive amount of wear on the seals, malfunctions of the main circulation pumps
were also reported; the rapid wear on ring seals made of tungsten carbide is accounted for by the high boron
content in the primary coolant. A satisfactory solution was found through the use of ring seals coated with
chromium oxide.
It is interesting to note that computer process monitoring of the operation of the Obrigheim nuclear
power station, using the Siemens-305 computer, shows much promise, with 450 analog variables monitored
and ?2200 binary signals processed.
Translated from Atomnaya Energiya, Vol.29, No.6, pp.470-471, December,1970.
43 1971 Consultants Bureau, a division of Plenum Publishing Corporation, 227 West 17th Street, New York,
N. Y. 10011. All rights reserved. This article cannot be reproduced for any purpose whatsoever without
permission of the publisher. A copy of this article is available from the publisher for $15.00.
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The symposium discussed cleanup of primary loop water at nuclear power stations. Since the com-
monly encountered water treatment systems using ion exchange, degassing, and evaporation equipment fail
to provide efficient filtration of active corrosion products, it was proposed that the problem be solved
through recourse to special mechanical filters.
A report presented by the Belgian concern Cocril?Ugrais ?Providence made a convincing demonstra-
tion of the advantages of upright steam generators; data on the advantages of inconel as a material in the
fabrication of steam generators, instead of the stainless steel AJSJ-316, were also presented.
Some of the reports dealt with improved design of water-cooled water-moderated reactors, and their
operation. Most of the authors of reports analyzing reasons for breakdown of heat processing and transfer
machinery at nuclear power stations, reach the unanimous conclusion that the overwhelming majority of
failures are due to insufficient knowledge of hydrodynamical phenomena, which are responsible for damaging
vibrations, generatedunder certain sets of operating conditions. Work is now underway everywhere on devel-
oping means and techniques for keeping a check on vibrations executed by the internal components of re-
actors and steam generators.
Lowering capital costs and improving the reliability of power station equipment are of vital signif-
icance in efforts to achieve economically competitive nuclear power. This explains the very serious atten-
tion being given to the building of more powerful high-efficiency and highly reliable steam turbines for nu-
clear power stations. Many of the papers presented by leading turbomachinery manufacturing concerns in
france, West Germany, Czechoslovakia, the USA, and Switzerland dealt with the design and fabrication of
low-speed turbines with extremely high specific power ratings, development and improvements in the de-
sign and fabrication of blading for the last stages of turbomachinery (TsND blading) of critically extended
blade length, general principles in the design of steam turbines for nuclear power stations, designs of last
stages, operating experience, and unitization and typization principles in the standardization of turboma-
chinery.
Most of the firms view the use of low-speed turbines (in the 1800 rpm or 1500 rpm speed range) as
correct for nuclear power stations, but justify this solely in terms of cost considerations, without bringing
into question the reliability of modern high-speed turbines. Maximum interest was evoked by a report sub-
mitted by the Czechoslovak Skoda works, containing extremely valuable information on the characteristics
of the exhaust stages of turbines with blades extending to 1000 mm in length, and with turbine runner speeds
up to 3000 rpm, depending on the choice of structural material and on the selection of blade fastening ar-
rangement. Results of an investigation of anticorrosion coatings for long blades designed for service in wet
steam, and designs of stator guide blading with suction drainage slits, are presented. Methods for elimi-
nating dangerous vibrations of turbine blades are described.
Valuable experience in coping with and overcoming defects in turbomachinery is communicated in a
report devoted to a description of startup operations at the Gundremingen nuclear power station (in West
Germany) centered around a 237 MW boiling-water reactor. Repeated failures and fractures of turbine
blades in the first stages of a cylinder of an AEG turbine at 1500 rpm resulted in repeated breakdown of
power station operations, with downtime lasting over nine months. The reason for the damage lay in pulsa-
tions of the stream of steam deriving from uneven moisture distribution in the piping leading to the TsND
(the existence of zones with moisture content as high as 12% when the average moisture content only
reached 1%). The introduction of changes in the design of the feed pipe connection brought about more uni-
form distribution of steam moisture; the design of the blade shanks in the first stages and runner disks of
TsND.
A report on heavy-water power reactors which presented Canadian experience in this area in a sys-
tematic manner evoked considerable interest as did a report on high-temperature gas-cooled reactors.
The French EdF concern, in a report shedding light on five years of operating history of basic heat
exchangers, drew the inference that the use of heat-transfer surfaces of complex configuration is not jus-
tified, because of difficulties in inspection and removal of flaws, and that efforts should rather be directed
to the design of simpler heat exchangers (specifically, smooth-tube exchangers are recommended).
The design of a Japanese experimental fast reactor with a power output rating of 50 MW(e) was also
of some interest.
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JUNE 1970 PRINCETON SYMPOSIUM ON PLASMA STABILIZATION
BY FEEDBACK AND DYNAMICAL TECHNIQUES
D. A. Panov
The extensive development undergone by research on methods for suppressing plasma instabilities by
feedback systems or by dynamic stabilization provided the basis for convening a symposium, organized
under the sponsorship of the Plasma Physics Laboratory of Princeton University, at Princeton (USA) in
June, 1970. The symposium drew participation from scientists of Britain, Italy, Norway, the Soviet Union,
France, and West Germany. Forty-eight papers were presented at the sessions of the symposium.
The work done by V. V. Arsenin and V. A. Chuyanov, and published in 1968 [1], has provided a stimulus
for developing research on feedback stabilization of plasma, and has furnished a basis for successful experi-
ments on suppressing flute instabilities in the plasma in the magnetic trap of the OGRA-2 thermonuclear
fusion machine [2]. The use of a feedback system to stabilize plasma instabilities was first proposed by
A.I.Morozov and L. S.Solov'ev in 1964 [3].
Work on plasma stabilization by feedback systems, as presented and discussed at the symposium,
touched on many questions ranging from classification of the stabilization mechanisms to the use of feed-
back in the study of specific modes of instability.
J. Taylor and C. Lashmore-Davis (Britain) showed that relevant feedback systems can be subdivided
into two types, active and reactive, depending on the modes of instability to be suppressed. Instabilities of
the interchange type, characterized by negative or positive energy of oscillation, belong to the first category.
The signal has to be phase-shifted ?90? in order to suppress such instabilities in a feedback system. The
choice of sign depends on the sign of the energy of oscillation. Instabilities of the interchange type charac-
terized by zero energy of oscillation being in the second category. The conclusion is that the allowable
phase shift for the stabilization of such stabilities is either 0? or 180?.
Most of the experimental papers presented at the symposium onthe subject of feedback dealt with ac-
tive plasma stabilization techniques. In those cases, it is possible to write out the dispersion equation
with the effect of the feedback loop taken into account, and to derive a theoretical dependence of the shift in
the real part of the frequency, of the size of the increment, and of the displacement of the instability thresh-
old, on the gain and on the phase shift in the feedback loop. An excellent concordance between measured
dependences and theoretically predicted dependences was demonstrated. The most typical results of that
sort are to be found in the papers submitted by T. Symonen (USA) and D. Jessby et al. (USA); these experi-
ments were conducted with alkali plasma generated in Q-machines. Similar results were communicated
in a report by B. Anker-Johnson et al. (USA).
A paper submitted by V. A. Zhil'tsov et al. (USSR) demonstrated that when a surface of finite conduc-
tivity is placed parallel to the boundary of a plasma, energy absorption in that surface due to the flowing
of induced currents in the surface will be greater, under optimized conditions, than the rate of increase in
the energy associated with unstable ion-cyclotron oscillations. At the same time, attenuation greater than
the instability growth rate is introduced into the plasma. The feedback loop will behave, at a certain phase
shift, like a surface of finite conductivity. Results of experiments on the suppression of an ion-cyclotron
instability in the plasma in the magnetic trap of the OGRA-2 thermonuclear machine were reported.
In most of the earlier experiments on suppression of instabilities by feedback, the control components
used were electrodes placed outside the plasma, or Langmuir probes immersed in the plasma. For under-
standable reasons, neither of these approaches is applicable to the case of a dense high-temperature plasma.
Translated from Atorrmaya Energiya, Vol. 29, No. 6, pp. 471-473, December, 1970.
o 1971 Consultants Bureau, a division of Plenum Publishing Corporation, 227 West 17th Street, New York,
N. Y. 10011. All rights reserved. This article cannot be reproduced for any purpose whatsoever without
permission of the publisher. A copy of this article is available from the publisher for $15.00.
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On that account, close attention was given in the reports presented at the symposium to techniques involving
electrodeless and contactless manipulation of the plasma. Reports by A. Huang et al. (USA) put forth results
of successful suppression of a trapping instability in an alkali plasma by microwave radiation at the upper
hybrid frequency (^.10 GHz) modulated by the feedback loop signal. A report by F. Cheng (USA) drew atten-
tion to the fact that direct utilization of microwave radiators to set up a contactless feedback loop is fraught
with difficulties in the case of a thermonuclear plasma. To cope with the problem, he suggested recourse
to a system of a pair of CO2 gas lasers situated in a such a way that the nonlinear interaction between the
two infrared laser rays would produce a difference frequency equal to the upper hybrid frequency of the
plasma. According to the estimates cited in the paper, the laser power output required to seriously affect
plasma oscillations is well within reasonable limits.
In the papers referred to above, as well as others submitted at the symposium, it was demonstrated
that the mechanism underlying active suppression of plasma instabilities characterized by either positive
or negative energy has been given sufficient study, as evidenced by the excellent agreement between theo-
retical calculations and experimental findings.
The experiments and theory of reactive feedback stabilization of plasma were presented in far less
generous volume. Only the reports by V. A. Chuyanov (USSR) and E. Murphy (Britain) gave information on
experiments dealing with stabilization of instabilities of that type, specifically flute instability of a plasma
in a magnetic field of a simple mirror configuration. A single-electrode feedback loop has been used suc-
cessfully in stabilizing the first mode of the plasma flute instability. But the suppression of flute instabili-
ties of the first mode is accompanied by a buildup of oscillations at other frequencies determined by the
characteristics of the feedback loop. Plasma losses accompanying the activation of the feedback loop are
smaller. In a theoretical paper, C. Lashmore-Davis (Britain) posed the question of the optimum frequency
response of a feedback loop for stabilizing a flute instability. But no satisfactory solution of this problem
meeting practical needs has been found.
Practically all of the work described in the experimental papers was done with the aid of a single feed-
back loop. A model of homogeneous boundary conditions was used, however, in the theoretical analysis of
the problem. The validity of the use of such a model was the subject of a paper, by J. Crowley (USA). The
example of a six-pole feedback loop designed to suppress plasma flute instabilities was brought up to show
that all modes of flute instability below the sixth mode can be suppressed provided the loop gain is above
a certain critical value. But flute oscillations with a mode number of seven or higher continue to build up,
even if the plasma density has not reached the level at which these oscillations become unstable when the
feedback loop is switched off.
Some of the reports presented results of a theoretical analysis of the feasibility of suppressing Kru-
skal?Shafranov instabilities in Tokamak type systems. A paper by J. Clarke and R. Dorey (USA) solved the
problem of stabilizing a corkscrew instability in a pinch, and showed that currents stabilized by a feedback
loop in a surface enveloping a plasma are capable of stabilizing unstable modes of oscillation which have
no radial modes. Practical realization of a system of that type would require first that some complicated
engineering problems be solved. G. Furth (USA) presented a brief review of problems pertaining to the use
of feedback loops to stabilize plasma instabilities in Tokamak machines. Among the other problems con-
sidered was the possibility of controlling currents in loops replacing the copper liner of Tokamak facilities
by a feedback system. The removal of the copper liner would open the way for using magnetic compression
in order to heat up the plasma more effectively.
Several theoretical papers dealt with the possible use of feedback where the feedback system is ac-
tivated only for very brief time intervals, to match signals from transducers recording displacements of
the plasma surface. Analysis of systems of the type described revealed that the difficulties attendant upon
stabilization of interchange instabilities by a linear feedback loophave been overcome to an appreciable ex-
tent. This problem was discussed in greatest detail in application to stabilization of plasma in Tokamak
type facilities, in a paper submitted by A. Milner (USA).
The use of high-frequency fields to stabilize plasma instabilities has been the object of research for
a fairly protracted period. This problem appears to have been tackled for the first time by S. M. Osovets
(USSR) back in 1957 [4]. Further development of this work can be traced in contributions of a theoretical
nature by Ya. B. Fainberg, V. D. Shapiro, V. P. Silin, L. I. Rudakov, and A. A. Ivanov (USSR), J. Teichman
(Czechoslovakia), and other authors as well.
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The problems touched upon in most of the theoretical reports presented at the symposium involve
improvements and refinements on work done earlier, or finding stabilization conditions applicable to spec-
ific experiments. Of greatest interest in this context was a theoretical report by A. A. Ivanov and V. F.
Murav'ev (USSR) which demonstrated that the ordinary wave and the helicon mode are capable of suppress-
ing electrostatic instabilities such that kz ? k, whenever the frequency of the mode excited is much higher
than the frequency of the instability. The example of a cone instability was brought up to show that recourse
to a helicon type mode is preferable, since the amplitude of the magnetic field on the wave in this case will
have to be lower.
There was great interest shown in a paper by M. Alcock and B. Keen (Britain) citing results on sup-
pression of a drift-dissipative instability in the plasma of the positive column of a discharge in helium and
in hydrogen, by means of a high-frequency azimuthal magnetic field. The natural frequency of the unstable
oscillations is 4 kHz. The frequency of the azimuthal magnetic field was varied over the range from 8 to
100 kHz. It was shown that the instability became suppressed, in harmony with the theory expounded by
A. A. Ivanov and J. Teichman, when the amplitude of the variable field came to ?1% of the amplitude of the
constant longitudinal field.
Suppression of the drift (trapping) instability by means of a high-frequency electric field with a fre-
quency higher than the ion plasma frequency was demonstrated in a report presented by the Japanese sci-
entists Y. Nishida et al. The experiments were carried out using the plasma of a gas discharge struck in
helium, at a particle density of 2 ? 109 to 5 ? 1010 cm-3.
Sausage type instabilities and helical instability in the hole plasma of indium?antimony semiconductors
placed in a magnetic field were suppressed with the aid of an HF field established by quadrupole conductors
such as Ioffe rodlets. The results of this work were presented in a paper by A. Anker-Johnson (USA).
The audience also showed keen interest in a report by G. Wolf (West Germany) which made available
the results of work on dynamical stabilization of a Rayleigh?Taylor instability in a heavy fluid above a
light fluid. High-frequency mechanical oscillations were impressed on the system in a direction parallel
to the interface separating the two liquid phases. While these mechanical vibrations were acting, the time
over which equilibrium of the heavy fluid over the lighter fluid was maintained was stretched to 104 times
the length of time in which large-scale instability ensued with the stabilization system deactivated.
The feasibility of stabilizing instabilities by impressing the high-frequency component of a longitu-
dinal magnetic field was studied in experimental papers presented by G. Becker et al. (West Germany) and
J. Phillips (USA). The feasibility of stabilizing an instability with the aid of the high-frequency field of a
linear quadrupole was also investigated, in the case of a Z-pinch. In both cases particle suppression of
the instabilities was achieved.
On the whole, the papers presented at the symposium constitute a valuable contribution to the further
development of research on methods for stabilization of plasma by systems using feedback and HF fields.
The promising possibilities of these methods were demonstrated in the study of specific instabilities, and
avenues open for utilizing these methods in future controlled thermonuclear fusion research were pointed
out. The proceedings of the conference are to be published as a separate edition.
LITERATURE CITED
1. V. V.Arsenin and V. A. Chuyanov, Dokl.Akad.Nauk SSSR, 180, 5 (1968).
2. V.V.Arsenin, V.A. Zhil'tsov, and V. A. Chuyanov, Plasma Physics and Controlled Nuclear Fusion Re-
search, Vol. 2, IAEA, Vienna (1969), p.515.
3. A. I. Morozov and L. S. Solov' ev, Zh. Tekh. Fiz., 34, 1566 (1964).
4. S. M. Osovets, Plasma Physics and Controlled Thermonuclear Fusion Studies, Vol.4, Izd-vo AN SSSR,
Moscow (1958), p.3.
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JUNE 1970 ZAKOPANE SYMPOSIUM ON NONDESTRUCTIVE
MATERIALS TESTING EQUIPMENT AND TECHNIQUES
USING NUCLEAR RADIATIONS
A. Maiorov
A symposium on nondestructive testing equipment and techniques using nuclear radiations was held
at Zakopane (Poland) in June, 1970. Participating in this symposium were specialists from member-na-
tions of COMECON, and 25 reports were presented and discussed.
Z. Pawlowski (Poland) delivered a review report, which pointed out that impressive advances may be
expected in the area of automation of radiographic, radiometric, and radio spectroscopic inspection work.
Attention was centered on the need to develop a method for determining the critical dimensions of flaws in
a variety of structural elements, and studying the effect of critical flaw dimension on the strength of the
structure inspected.
E. Becker (East Germany), presenting a historical survey of the development of radiography over the
past half-decade, voiced the suggestion that it will be difficult to expect any radical improvements in this
method in the immediate future. L. Brunarski et al: (Poland) and A. N. Maiorov (USSR) devoted their re-
ports to optimization of radiographic conditions, which stimulated deep interest in those attending the sym-
posium, who acknowledged the need to develop a unified procedure and unified recommendations in this
area of work.
In a joint report by Polish and USSR specialists, L. Brunarski, L. M. Serebrennikov, et al. expounded
the fundamentals of supervision of the use of radiographic quality control work applied to concrete and re-
inforced concrete structures. A list was drawn up of the equipment needed in the radiographic inspection
of concrete, the general technical conditions to be observed in testing work, procedures for measuring the
thickness of concrete, the diameter of reinforcing rods and wires and the depth to which they are laid in the
concrete, detection of internal voids, and basic points in safety practice in the testing of structural mem-
bers
V. G. Firstov et al. (USSR) reviewed the present level of work in the area of xeroradiography, and
cited data on the PKR-1, ERGA-S, EGU-6m, KS-1 xeroradiographic machines manufactured in the Soviet
Union. The characteristics of similar machines manufactured in the USA, Britain, and Japan were sur-
veyed at the same time. E. Gusew (Poland) reported on xeroradiographic equipment manufactured by the
Lodz xerography factory. It was reported that the Pyloris (KS-2 and KS-4) xeroradiographic machines de-
veloped by the Electrical Engineering Institute, with their stagewise methods of image development, are
being used in industrial inspection work in the Polish Peoples Republic. Even today, the level attained in
the development of techniques has opened the way clear for the use of xeroradiography in nondestructive
testing work.
Z. Godlewski and B. Kaminski (Poland) reported results of work done at the Electrical Engineering
Institute; there radiometric flaw detection instruments have been developed for the inspection of active
specimens, tungsten nozzles, refractory materials, and carbon blocks. The sources used in these instru-
ments are Co", Cs137, Ir192, Tm170, and Am241. Information was cited on the development of radiometric
flaw detection instruments in East Germany for inspection of steel plate, and for inspection of tubes and
tanks in Japan, as well as instruments for inspection of rolled goods at metallurgical plants in France and
in West Germany, and joint development of radiometric flaw detection instrumentation for inspection of
steel blooms by Czechoslovak and Polish industry.
Translated from Atomnaya Energiya, Vol. 29, No. 6, pp. 473-474, December, 1970.
o 1971 Consultants Bureau, a division of Plenum Publishing Corporation, 227 West 17th Street, New York,
N. Y. 10011. All rights reserved. This article cannot be reproduced for any purpose whatsoever without
permission of the publisher. A copy of this article is available from the publisher for $15.00.
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A report by V. G. Firstov et al. analyzed the feasibility of applying radiometric flaw detection tech-
niques to nondestructive testing andinspection of blooms in the rolling process, to centrifugally cast tubing
in mass production, and to unreinforced welded seams Spectrometric, spectrometric-count, and collima-
tion-spectrometric procedures in radiometric flaw detection work were discussed, and a procedure was
worked out for calculating sensitivity and productivity in inspection work, illustrated by graphs of the de-
pendence of inspection productivity on the minimum dimensions of flaws to be discerned and on the dimen-
sions of the collimation hole.
Despite the successes attained in experimental and theoretical research on methods of radiometric
flaw detection, to date we still lack quantity-produced equipment to carry out this work on a routine scale
in industry, and this is accounted for by the lack of highly efficient radiation detectors, a lack of high-speed
electronic equipment featuring small instrument fluctuations and excellent sensitivity to insignificant
changes in the signal arriving for processing, and a lack of low-energy sharply focused sources of high
specific activity which might contribute to improved resolution and greater productivity at the same time.
Visual methods of nondestructive testing and inspection were discussed at the symposium in reports
delivered by J. Ginsztler, "Visual methods of inspection in industrial radiography," and J. Sorm (CSSR),
"Application of an image brightness intensifier in inspection of castings." The Czechoslovak "Tesla" firm
has now achieved industrial-scale production of the 03QA41, 040QA41, and 05QA41 type electronic image
converter tubes with tube dimensions ranging from 175 to 289 mm, which can be used profitably in visual
monitoring and inspection arrangements. The observed trend of development of visual techniques shows
that further improvements in radioscopy (radiographic flaw detection work) will be impossible either in
the field of new developments or in the area of incorporating existing advanced equipment in regular inspec-
tion practice, without first developing the instruments and equipment needed to eliminate the subjective
fact in assessments of flaws, and thereby opening the way to proceed ahead to automatic computing of all the re-
lated data. To a lesser extent this will obtain to its application in the location and classification of flaws in parts.
A report by A. Jedziewski (Poland) provided a description of the Polish IP-8, IP-25, CP-1, and CP-10
type hose-attachment y-ray flaw detection instruments with pneumatic feed of TH192 and Con radiation
sources to the irradiation target up to distances of 30 m. These sets use lead shielding. At the present
time, a modified variant of these y-ray flaw detection instruments using uranium shielding is under develop-
ment. These sets are intended mainly for use in production shops where assembly and rigging of outsize
equipment and structures are handled. Four types of Polish flaw-detection equipment were demonstrated
at an exhibit set up at the symposium; also demonstrated were two negative viewers for decoding radio-
graphic images with photographic density up to three and up to five. The first type of negative viewer has
a rectangular light field controlled by adjusting blinds, and a photocell for excluding light, while the second
type of negative viewer has a diaphragm-controlled circular field.
R. Dubenski (CSSR), in his report "Stereoscopic viewer for x-ray plates," discussed a stereoscope
for simultaneous viewing of two radiographic images made by the method of lead markers. The prere-
quisite for working with the stereoscope is unimpaired vision and space perception ability on the part of
the operator. The report also provides a description of a stereoscope relying on the principle of polariza-
tion of light; the operator dons polarized eyeglasses, and the radiographic images are projected onto a
screen with a metallized silver coating. In addition, a stereoscopic negative viewer in which a mirror sys-
tem is used to combine and transpose the images is described. These instruments were developed at the
Higher Technical School in Prague, and are used to pinpoint the location of flaws in radiographed products.
V. N. Khoroshev et al. (USSR) provided information on completed development work on y-ray nonde-
structive testing instruments in the COMECON normal classification RID-11, RID-21, RID-22, and (RID-32),
on sets of equipment for irradiation of piping and tanks of large diameter (the Gazprom, Trassa, and Neva
sets), specialized equipment for frontal transmission (the Stape11-5 and Stapele-20), and hose-attachment
automated y-ray nondestructive testing instruments (the Labirint and the Kama).
A report by W. Listwan and M. Dobrowolsk (Poland) presented results of joint research and develop-
ment work of Polish and Czechoslovak specialists on radiometric equipment for inspecting communications
cables and piping while these are in service. The method is based onthe introduction of radioactive tracers
with a short half-life into the piping, through which various gases of petrochemicals, etc., are pumped, the
concentrations of these tracers in the medium surrounding the piping and subsequent detection of the affec-
ted portion of piping by means of a radiometric instrument inserted into the piping and moving through the
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'nterior of the piping under the pressure of the gas or liquid being pumped through. The method has been
tested and has been accepted on an experimental production basis in the Czechoslovak and Polish sections
of the Druzhba international pipeline, as well as on other gas pipelines.
A report by N. D. Tyufyakov et al. (USSR) cited results of research work on neutron radiography, going
in particular into a detailed discussion of neutron sources, the dependences of slow-neutron beam charac-
teristics on beam shaping conditions, and production of beams with optimized properties; the paper also
covers determinations of neutron scattering factors, inspection sensitivity, nomograms of exposures for
use with detectors of neutron images that have been developed, and goes into a discussion of the range of
applicability and convenience of the method. A. Petrov (Bulgaria) cited information on the joint development,
in the USSR and Bulgaria, of lightweight transportable flaw-detection laboratories designed for mounting
on the UAZ microbus, and the medium weight type laboratory designed for mounting on a large panel truck,
and equipped with a set of varied flaw detection equipment.
Several of the reports were devoted to the present utilization, and outlook for future utilization, of
radioisotope, x-ray, and betatron nondestructive testing equipment and techniques in construction, boiler
manufacture, aviation, foundry work, and in other branches of industry in the member-nations of the Council
for Mutual Economic Aid (COMECON).
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THE SATURN-1 PLASMA MACHINE
V. A. Suprunenko
The Saturn-1 toroidal triple-loop stellarator for plasma research was commissioned at the Kharikov
Physicotechnical Institute in the first half of 1970. The distinguishing feature of this plasma machine is its
capability of operating in two modes: the stellarator mode and the torsatron mode. In the first mode,
magnetic surfaces with large and controlled "shear" values (.50.15) and a rotational transform angle of the
lines of force (.5.1.3 r) are established in the effective volume of the machine. In the second mode, surfaces
with "shear" (-0.1) and with a "magnetic potential well" (-10%) are established. The maximum intensity of
the longitudinal magnetic field in the quasistationary mode attains the level of 10 k0e. The inner diameter
of the vacuum chamber is ?170 mm.
The first results of research on the magnetic surfaces revealed excellent agreement with theoretically
predicted parameters, as clear evidence of the high precision with which the magnetic trap was fabricated.
Translated from Atomnaya nergiya, Vol. 29, No. 6, p.474, December, 1970.
O 1971 Consultants Bureau, a division of Plenum Publishing Corporation, 227 West 17th Street, New York,
N. Y. 10011. All rights reserved. This article cannot be reproduced for any purpose whatsoever without
permission of the publisher. A copy of this article is available from the publisher for $15.00.
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THE ANGLO-SOVIET PLASMA PHYSICS EXPERIMENT
V. V. Sannikov
From February through December 1969, an experiment designed for determining the electron tem-
perature and density of a plasma, and also to determine the radial distribution of the plasma pinch by the
method of Thomson scattering of laser emission, has been staged by a team of physicists from Culham
Laboratory, including Drs. N. D. Peacock, D.C. Robinson, P. D. Wilcock, and M.D. Forrest, in collaboration
with colleagues of the I. V. Kurchatov Institute of Atomic Energy (IAE), at that latter institute. This method,
in contrast to those used earlier, made it possible to measure the electron temperature and density of the
plasma directly.
British equipment was installed on the Tokamak T-3 plasma machine (large radius 1 m, small radius
25 cm, diaphragm radius 17.5 cm).
With the plasma parameters of this machine Te ? 102 to 2 ? 103 eV, ne ? 1013 to 5 ? 1013 cm3, the Sal-
peter coefficient a = X0/4/rADsin0/2 ? 1, where A = 6943 A; AD is the Debye radius; 0 is the scattering
angle (0 = 90?). The case of scattering on free electrons was realized here. The scattered radiation spec-
trum is described by a Gaussian curve, with a Maxwellian distribution of electron velocities assumed.
A beam of light with a divergence of 2.5 mrad was directed from a ruby laser operated in the giant
pulse mode, with radiation energy 5 J and pulse duration 20 to 30 msec, through the plasma pinch diametral-
ly. Radiation scattered at 90? was recorded from a plasma volume of 1 cm3 by means of collimating optics
and a wide-aperture spectrograph with a ten-channel photoelectric system for recording the spectrum.
The spectral width of each channel was 78 A.
Half the Gaussian curve was taken from the shortward end of the spectrum, from the laser emission
line 6943 A. The spectrum was recorded in a single current pulse simultaneously on all the channels. The
intensity of the hydrogen line Ha was measured in one of the channels.
The electron concentration in the plasma was estimated from the ratio of the absolute values of the
energy of the scattered light and the energy of laser emission.
A special periscopic viewing system was set up so as to obtain the radial temperature distribution
and radial distribution of electron density in the plasma. The distribution of concentration was recorded
at the same time by a multichord two-millimeter interferometer. Data on density obtained with the laser
and with the microwave interferometer were in close agreement.
The measured electron temperature of the plasma ranged from 100 to 2000 eV, depending on the dis-
charge conditions. The plasma concentration ranged from 1013 to 4.5 ? 1013 cm-3, while the current ranged
from 40 to 150 kA, and the intensity of the longitudinal magnetic field from 17 to 38 k0e.
It is to be noted that the experimental data points fit closely to the theoretical Gaussian curve, with-
in the limits of error of the measurements. This might mean that a Maxwellian distribution of electron
energies prevails in this instance. The electron temperature increases to a maximum in 12 msec, and re-
mains practically constant until the discharge current has died away completely.
The radial temperature distribution and radial electron density distribution are sufficiently flat near
the axis of the pinch, and diminish monotonically toward the periphery of the pinch. The temperature in-
creases as the discharge current, roughly in obedience to the law 12 (dependences were taken at current
pulse widths of 35 and 70 msec), and varies inversely with the plasma density.
Translated from Atomnaya Energiya, Vol.29, No. 6, p.475, December, 1970.
0 1971 Consultants Bureau, a division of Plenum Publishing Corporation, 227 West 17th Street, New York,
N. Y. 10011. All rights reserved. This article carinot be reproduced for any purpose whatsoever without
permission of the publisher. A copy of this article is available from the publisher for $15.00.
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The electron temperature of the plasma is virtually independent of the longitudinal magnetic field.
The experiment was performed under conditions featuring high anomalous resistance presented by the
plasma. The plasma temperature as calculated on the basis of conductivity in all the sets of conditions
investigated is lower than the temperature measured with the laser, and varies slightly over the current
pulse. It amounts to 100-200 eV, depending on the operating conditions.
The electron temperature distribution was measured every 4 msec after the onset of current under
various sets of conditions, giving some indication of slight "skinning" of the temperature near the edge of
the pinch, but no clearcut "skinning" effect was obtained in later experiments, since measurements earlier
in time were impossible on account of the high level of the plasma's intrinsic radiation, while measure-
ments taken later than 4 msec yielded a flat distribution near the axis. The rapid levelling off of tempera-
tures is an indication that the electron thermal conductivity of the plasma is well above the classical value.
The particle lifetime found from measurements of the absolute intensity of the Ha line was 15 to 20
msec, and was longer than the energy-derived plasma lifetime of 5 msec.
Data on the radial distribution of the temperature and electron density of the plasma were utilized
in computing the transverse energy of the plasma as a function of the time. The transverse component of
the energy was determined simultaneously from the diamagnetic effect of the plasma. The energies mea-
sured by these two independent techniques were found to be in satisfactorily close agreement.
Note that the data on plasma parameters obtained by the method of laser scattering confirmed the
results obtained earlier by Soviet physicists relying on rival methods.
LITERATURE CITED
1. Nature, 224, No. 1, 488-490 (1970).
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GKIAE ?JINR AGREEMENT ON SCIENTIFIC AND
TECHNICAL COLLABORATION
V. Biryukov
An agreement on scientific and technical collaboration was signed at Dubna,in June 1970, between
the State Committee on the Peaceful Uses of Atomic Energy [GKIAEJ and the international physics research
center of the socialist countries, the Joint Institute for Nuclear Research [JINR]. The purpose of this agree-
ment is to "contribute to the rounded all-sided development of scientific and technical collaboration between
member-states of JINR by combining the efforts of JINR scientists and scientists working in GKIAE-super-
vised institutes. ." The two parties signatory to the agreement state that they will "jointly develop sci-
entific and technical collaboration in the field of nuclear physics, for the maximum and most efficacious
utilization of accelerators, nuclear research reactors, equipment for experimental data processing, and
other experimental and research facilities at their disposal, and will also devise new equipment for those
purposes. . . ."
Specific efforts will be undertaken and expedited on the basis of bilateral contracts or protocols con-
cluded between JINR and institutes under GKIAE, to determine the scope, times, and conditions of this re-
search. The contracting parties, in attainment of mutual agreement, agree to draw upon national or inter-
national research organizations and other bodies in carrying out this joint work, and will observe the prin-
ciples of reciprocity and take into account the interests of the parties involved. Institutes in member-na-
tions of JINR engaged in collaboration with JINR and drawn into the overall scientific plans approved by
JINR may also be included in the work carried out jointly by the two signatories.
The agreement lays down the general obligations of the two contracting parties on establishing the
prerequisite conditions for work on accelerators and other research facilities: the operation and servicing
of the equipment, providing electric power, liquefield gases, tool shops, computer and data processing op-
erations, making available the necessary scientific and technical information for this joint work, and so
forth. GKIAE will assist JINR and the institutes preparing this joint research in the development and fabri-
cation of experimental equipment needed.
In line with the agreement signed, the contracting parties will sponsor annual meetings of their re-
spective representatives and experts, for discussion of concrete problems in scientific and technical col-
laboration.
The agreement extends over a five-year period, and will be automatically extended another term of
equal length, if neither of the two signatory parties voices an intention of terminating the agreement.
The international juridical document signed at Dubna flows both in spirit and in content from the
famous 1959 Moscow agreement on the organization of the Joint Institute for Nuclear Research, and will
serve the cause of further development of scientific and technical collaboration between the socialist coun-
tries.
Translated from Atomnaya Energiya, Vol. 29, No. 6, pp. 475-476, December, 1970.
O 1971 Consultants Bureau, a division of Plenum Publishing Corporation, 227 West 17th Street, New York,
N. Y. 10011. All rights reserved. This article cannot be reproduced for any purpose whatsoever without
permission of the publisher. A copy of this article is available from the publisher for $15.00.
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BRIEF COMMUNICATIONS
An All-Union science and engineering seminar was held at the "Atomic Energy" pavilion of the Ex-
position of Achievements of the National Economy of the USSR in July 1970, on the topic "Methods and equip-
ment for dosimetric monitoring of radioactive radiations and x-rays," with 66 organizations participating.
In a review report, V. V. Matveev discussed general topics concerning the development of complex dosimet-
ric and radiometric systems, design of functional modules with unified dimensions, and characteristics of
instruments developed at the All-Union Research Institute for Instrument Design.
The participants at the seminar discussed various methods for calibrating dosimeters and radio-
meters, requirements applicable to dosimetric inspection and checkout systems, design of dosimeters,
whole-body spectrometers, etc.
* * *
An All-Republic seminar of workers in chemical plants was held in Kiev in June 1970 on the topic
"Radioisotope techniques and instruments in the chemical industry of the Ukraine."
The seminar participants reported that radioisotope techniques and instrumentation have been making
their way in recent years in production use at advanced chemical processing plants such as the Severo-Do-
nets Chemical Combine, and the Kaluga Chemical-Metallurgical Combine, where applications of radioiso-
tope instruments are yielding impressive savings and improving working conditions.
* * *
A seminar was held in Moscow in June 1970 to expedite exchanges of experience in the operation of
in-plant and base isotope laboratories, and the implementation and acceptance of new methods and radio-
isotope techniques and equipment in industrial process monitoring. Participating in the seminar were 84
organizations and industrial plants under various ministries and departments, whose representatives re-
ported that the national economy of the country has already been benefiting from applications of radioiso-
tope techniques in terms of impressive savings, and that both base and in-plant isotope laboratories have
had a positive effect on the acceptance of atomic science and engineering in industry.
* * *
A science-familiarization excursion organized for the benefit of specialists from developing countries
with membership in IAEA and FAO took place from August 6 through August 31, 1970, under the joint aus-
pices of the State Committee on the Peaceful Uses of Atomic Energy of the USSR [GKIAE] and the Ministry
of Agriculture of the USSR, affording an opportunity for these specialists to be brought up to date on appli-
cations of isotopes and radiations in agriculture in various locations throughout the Soviet Union. The group
included scientists from Brazil, Chile, Costa Rica, Ghana, India, Iran, Lebanon, Mexico, Pakistan, Philip-
pines, Sierra Leone, Sudan, Thailand, the United Arab Republic, and Yugoslavia, as well as leading staff-
members of both IAEA and FAO.
One-day seminars at which lectures were delivered on applications of heavy water in soil and agro-
chemical research, applications of techniques and equipment for radiation work in agriculture, the study of
the transformation and use by plant life of nitrogenous fertilizers through the use of such isotopes as N15,
P32, C14, etc., were organized in the course of the trip for the participants.
The program included visits to Moscow-area scientific research institutes such as the V. V. Dokuchaev
Soil Science Institute, the isotopes laboratory of the All-Union Scientific Research Institute for Electrifica-
tion of Agriculture [VNIIESKh], the D. N. Pryanishnikov All-Union Scientific Research Institute for the study
of Fertilizers and Agronomical Soil Science, the Institute of Genetics and Plant Selection of the Siberian
Division of the USSR Academy of Sciences (in Novosibirsk), the Biology and Soil Science Department of
Translated from Atomnaya Energiya, Vol.29, No. 6, p.476, December, 1970.
o 1971 Consultants Bureau, a division of Plenum Publishing Corporation, 227 West 17th Street, New York,
N. Y. 10011. All rights reserved. This article cannot be reproduced for any purpose whatsoever without
permission of the publisher. A copy of this article is available from the publisher for $15.00.
1263
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Moscow State Unoversity, the V/O Izotop agency exhibit hall, the Exposition of Achievements of the National
Economy of the USSR, and the P. Lumumba University.
A discussion of the organization of scientific research work utilizing isotopes in agriculture was
held at the V. I. Lenin All-Union Academy of Agricultural Sciences. [VASICINIL].
* * *
An agreement between Sweden and the Soviet Union covering a thirty-year period of collaboration in
the area of peaceful uses of atomic energy was concluded in September 1970. Agreement on signing this
convention was reached in the course of a visit to Sweden by the Chairman of the Council of Ministers of
the USSR, A. N. Kosygin, in the summer of 1968.
Agreement envisions the possibility of both parties delivering and obtaining equipment, including
nuclear reactors and fuels for nuclear reactors, nuclear materials, nuclear raw materials, and special nu-
clear materials of commercial interest. The Soviet Union will provide services in enriching Swedish-ac-
quireduranium at plants in the USSR. The practical realization of this collaboration will be spelled out in
further agreements, protocols, or contracts.
In accordance with the Treaty on nonproliferation of nuclear weapons, Sweden and the Soviet Union
have decided to turn to IAEA with a request to carry out the provisions of the Treaty on inspection and con-
trol of the utilization of nuclear materials and equipment delivered under the terms of this agreement.
1264
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INDEX
SOVIET ATOMIC ENERGY
Volumes 28-29, 1970
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Declassified and Approved For Release 2013/04/09: CIA-RDP10-02196R000700060001-1
AUTHOR INDEX
A
Ado, Yu. M.-163
Adiyasevich, I. K.-74
Akhachinskii, V. V.-314, 1211
Akimov, I. S.-412
Akimova, R. I.-727
Aleinikov, V. E.-557
Aleksandrov, I. A.-712
Aleksandrov, L.-914, 1010
Alekseev, A.E.-172
Alekseev, B. A.-1235
Alekseev, V.I.-412, 1067
Aleksin, V. F.-25
Anan'ev, V. D.-1012
Anant in, V. M.-941
Andreev, V. D.-608
Andriushchenko, V.1.-818
Anikin, G. V.-532
Antonov, A. V.-910
Arabei, B. G.-1026
Arnol' dov, M. N.-20
Arsen'ev, Yu. D.-528
Arsenin, V. V.-175
Arsent'ev, I. N.-210
Artyushov, G. A.-1240
Aseev, G. G.-654
Averkiev, V. P.-708
Babulevich, E. N.-172
Bak, M. A.-297, 460
Bakhurov, V. G.-83
Bakulevskii, A. A.-14
Balandin, G. S.-198
Baranov, V. F.-301, 302
Baranov, Yu. L-297
Barchugov, V. V.-816
Barkov, S. N.-64
Basargin, Yu. G.-809
Bashlykov, S. N.-1211
Bass, L. P.-53
Batalov, A. A.-1016
Beer, A. A.-1240
Belous, V. N.-14
Belovintsev, V. Ya.-635, 810
SOVIET ATOMIC ENERGY
Volumes 28-29, 1970
(A translation of Atomnaya nergiya)
Bel'skaya, E. P.-74
Belyaev, A. A.-303
Bevz, A. S.-171
Bezel 'nitsyn, V. N.-86
Biryukov, E .1.-457
Biryukov, 0. V.-25
Bobkov, V. G.-1009
Bogatyrev, V. K.-140
Bogdanov, F. F.-1229
Bogdanov, V. G.-462
Bogdanova, V. I.-809
Bolotova, N. G.-1243
Bol'shov, V.1.-497
Bondarenko, N. P.-301
Borodin, V. E.-643
Bortsov, V. G.-531
Bosamykin, V. S.-549
Bredikhin, M. Yu.-1003
Breger, A. Kh.-331, 624
Bugorkov, S. S.-462
Buleev, N.1.-683
Bulgakov, Yu. V. -221
Burchenko, P. Ya.-156
Burmagin, L. 1.-301
Bushuev, A. V.-531
Bushuev, N. 1.-1129
Bychkov, V. A.-135
Bychkov, N. V.-180, 622
Chaivanov, B. B.-630
Chalupa, B.-523
Chapnin, V. A.-641
Chavychalova, T. P.-986
Chechetkin, Yu. V.-699, 776
Chechetkina, Z. I.-882
Cherkasskii, A. Kh.-1225
Chernobrovkin, V. V.-537, 786
Chernyaev, S. V.-1227
Chernyaev, V. A.-528
Chernyaev, V. B.-205
Chesnokov, I. S.-1227
Choporov, D. Ya.-71, 189
Chuburkova, I. L-990
Chuchalin, I. P.-727, 826
Chudinov, E. G.-71, 189
Chudinov, V. G.-537, 786
Chukichev, M. V.-641
Chultem, D-1035
Churakov, G. F.-25
Churin, S. A.-54, 913
Daruga, V. K.-1233
Davidenko, V. A.-135, 195, 866
Deev, Yu. S.-1037
Demidov, A. M.-145
Demikhovskii, D. A.-998
Demin, V. E.-1121
Dem'yanenko, G. K.-847
Denis ik, S. A.-55
Denprovskii, I. S.-210
Desyatnik, V. N.-317
Dideikin, T. S.-932
Didenko, A. N.-339
Dimov, G. L-1100
Dmitriev, A. V.-208
Dmitriev, P. P.-333, 335, 637, 916
Dmitriev, V. M.-497
Dmitrieva, Z. P.-333, 335, 637
Dmitrievskii, V. P.-858
Dnestrovskii, Yu. N.-1205
DobrovoI'skii, V. F.-621
Dogaev, Yu. D.-51, 52
Dolgikh, P. F.-83, 1140
Dovbenko, A. G.-532
Dovzhenko, A. S.-981
Drapchinskii, L. V.-462
Dreval, I. D.-536
Drozdov,V. E.-625
Druin, V. A.-837
Dubinin, A. A.-497
Jubovskii, B. G.-140
Dubrovskii, B. G.-412
Dubrovskii, V. B.-336
Dudnikov, V. G.-1100
Dunaev, L. M.-625
Duvanov, V. M.-531
Dvinyaninov, B. L.-299
Dvornikov, A. F.-304
D'yachenko, P. P.-835
Dymkov, Yu. M.-539
1267
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Declassified and Approved
Dzantiev, B. G.-763
Dzhelepov, V. P.-858
Efanov, A.1,-57
Efimenko, B. A.-1013
Egorov, Yu. A.-216
EmePyanov, I. Ya.-1067
Ermagambetov, S. B.-1190
Ermakov, V. I.-918
Ershov, Yu. 1.-534
Evseev, A. Ya.-412
Evstyukhin, A.1.-262
Ezhov, V. K.-629
FauP shtikh, Kh.-431
Fedorenko, A.1.-510
Fedorov, A. A.-542
Fedorov, M.1.-1022
Fedorova, L. A.-491
Feller, L.-440
Feinberg, S. M.-870
Feofanov, A. P.-312
Fiks, M. M.-1199, 1245
FilM, Yu. P.-633
Filippova, N. V.-1223
Flerov, G. N.-390, 967
Fomenko, V. T.-76
Fominykh, V.1.-201
Fradkin, G. M.-986
Fridman, Sb. D.-840
Frolov, Yu. G.-794
Frolov, V. V.-140
Frunze, V. V.-623
Gabeskiriya, V. Ya.-259
Gacs, F.-440
Gadzhokov, V.-914
Gaidamachenko, G. S.-886
Ganichev, G.1.-739
Garber, R. I.-510, 516
Gavrilov, K. A.-464, 502
Gavrilov, N. V.-794
Generozov, V. L.-226
Georgievskii, A. V.-25
Gerasimov, A.1.-549
Gerasimov, V. F.-150
Gerasimov, V. V.-14, 923
Gladkov, V. P.-941
Glushkov, E. S.-64, 1116
Goganov, D. A.-78
Goltdanskii, V.I.-858
Golovchenko, Yu. M.-135, 886
GoPtsev, V. P.-882
Gommershtadt, V. Ya.-55
1268
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Gomozov, L.1,-1131
Goncharev, L. A.-172
Gorshkov, V. K.-88, 639
Goryunov, E. F.-539
Goshchitskii, B. N.-786
Govor, L. I.-145
Grachev, M.1.-712
Granatkin, B. V.-910
Grinberg, E. M.-829
Grishaev, I. A.-648, 847
Gromova, A. I.-14
Gubrienko, K.1.-712
Gusev, V. V.-537, 786
Havkin, V. S.-1111
Ibragimov, Sh. Sh.-336
Ignatenko, A. E.-915
Ignatov, A. A.-689
IPchenko, A. M.-1003
Inozemtsev, V. F.-1240
Iovnovich, M. L.-1199, 1245
Isaev, N. V.-689
Ivannikov, R. I.-91
Ivanov, L. I.-829
Ivanov, R. N.-259
Ivanov, V. A.-145
Ivanov, V. E.-886
Ivanov, Yu. S.-1248
Ivanovskii, M. N.-20
Ivanovskii, N. N.-925
Kabanov, G. L.-228
Kafengauz, N. L.-1022
Kalashnikov, L. N.-31
Kalinin, N. N.-1236
Kaminker, D. M.-454
Kanashin, Yu. P.-1011
Kapchigashev, S. P.-497
Karalova, Z. K.-259
Karasev, V. S.-510, 516, 1221
Kargin, A. N.-1129
Karnaukhov, V. V.-727
Kashcheev, I. N.-51, 52
Kaspernovich, A. I.-622
Katrich, M. P.-31
Katsaurov, V. I.-320
Katsitadze, Dzd. G.-60
Kazachkovskii, 0. D.-528
Kazakova, L. Ya.-532
Kazarnovskii, M. V.-910
Kazazyan, V. T.-763
Kazmovskii, S. P.-9
Kessel' man, V. S.-221
IChaikovich. I. M.-174, 739
Kharchenko, V. A.-326
Kharin, V. P.-918
Kharitonov, N. P.-893
Kharitonov, Yu. P.-837
Khavkin, V. S.-1220
Kherfort, L.-431
Kheteev, M. V.-1112
Khisamutdinov, A. I.-1222
Khiznyak, N. A.-654
Khmaruk, V. G.-845
Khmyzov, V. V.-719
Khokhlov, Yu. A.-938
IChokhlov, Yu. K.-723
Khovanovich, A. I.-635, 1113
Khristov, V.-1010
Khrudeva, G. A.-88
Khudyakov, A. V.-198, 1024
Kimel', L. R.-557, 643, 1115
Kirichenko, G. S.-845
Kirillov, E. V.-529
Kirilyuk, A. L.-186
Kisil' , I. M.-412
Kitaevskii, L. Kh.-25
Klement'ev, A. P.-549
Klimanov, V. A.-1013
Klimenkov, V. I.-882, 1024
Klimentov, V. B.-1009
Klinov, A. V.-623
Knyazev, V. A.-699
Kobzar' , I. G.-776
Kogan, R. M.-840
Kokhlov, V. F.-689
Kokovikhin, V. F.-635, 816
Kolesov, B. I.-14
Kolesov, B. M.-739
Kolesov, I. V.-502, 967
Kolesov, V. E.-532
Kolokol'tsov, N. A. - 832, 1032,
1193
Kolomenskii, A. A.-1095
Kolyada, V. M.-510, 516
Kolyadin, V.I.-1016
Komar, E. G.-25
Komochkov, M. M.-557
Kondrat'ev, B. S.-817
Kondurushkin, N. A.-635, 816
Konobeevskii, S. T. -418, 773
Kononenko, S. G.-554
Konoplev, K. A.-454
Konotop, Yu. F.-886, 1184
Konovalov, E.-307
Kon'shin, V. A.-497
Konstantinov, I. 0.-333, 335, 916,
1114
Konstantinov, L. V.-57, 412, 537, 786,
1067, 1227
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Declassified and Approved For Release 2013/04/09: CIA-RDP10-02196R000700060001-1
Kopchinskii, G. A.-1009
Kopylov, V. S.-307
Kopytin, L.M.-314
Korenevskii, V. V.-336
Kormushkin, Yu. P.-623
Kornienko, L. A.-195
Korobkov, I. L-262
Korolt, K. N.-809
Koroleva, V. P.-630
Korotaev, S. K.-9
Korotaeva, M.N.-307
Korotovskikh, P. M.-537, 786
Korychanek, J.-1124
Korzh, P. D.-76
Koshaeva, K. K.-464
Kos ik, N. A.-31
Kostomarov, D. P.-1205
Kostrits a, A. A.-454
Kostyukov, N. S.-722
Kosulin, N. S.-773
KotelTnikov, G. A.-1019, 1235
Kotel'nikov, G. N.-1135
Koteltnikov, V. V.-1243
Kotikov, P. I.-699
Kovalev, V. P.-918
Kozhenkov, N. N.-1235
Kozhevnikov, D. A,-1111
Kozhevnikov, A. V.-339, 1146
Kozhevnikov, D. A.-1220
Kozlov, F. A.-925
Kraitor S. N.-464
Kramer-Ageev, E. A.-719
Kramerov, A. Ya.-718
Kramov, N. N.-457
Krasin, A. K.-'763
Krasnov, N. N.-333, 335, 637,
916, 1114
Krasnov, Yu. N.-530
Krasovitskii, V. B.-551
Krishtal, M. A.-829
Krivokhatskii, A. S.-297
Kroshkin, N.1.-790
Krotikov, V. A.-893
Kruglyi, M. 5.-1037
Krupman, A.1.-303
Kryvokrysenko, I. F.-1113
Kudinov, V. V.-301
Kudryavstsev, A. P.-192, 730
Kudyakov, V. Ya.-530
Kulikov, I. A.-544
Kul,kina, L. P.-534
Kulekov, A. D.-915
Kuptsov, V. M.-843
Kurilko, V. I.-631
Kursakov, V. N.-1144
Kushin, V. V.-536, 823
Kutner, V. B.-91
Kuz'min, A. A.-1248
Kuzmin, V. L-50, 446
Kuz' minov, B. D.-835
Kuznetsov, E. K.-925
Kuznetsov, V. I.-91,534
Kuznetsova, G. G.-654
Ladygin, A. Ya.-336
Lagunstov, N.1,-1032
Laletin, N. 1.-309
Lapiashvili, E. S.-60
Laptev, V. G.-699
Laskorin, B. N.-491
Lavrenikov, V. D.-1010
Lazarev, Yu. A.-502, 967
Lebedev, I. G.-446
Lebedev, V. N.-643
Lebedeva, N. S.-398
Lebenko, P. I.-708
Leipunskii, A. I.-384
Leman, E. P.-219, 1243
Lenchenko, V. M.-721, 742
Leonov, V. F.-1019
Levchenko, V. B.-683
Levitskii, B. M.-418
Levskii, L. K.-443
Lezhava, A. N.-60
Lipanina, A. A.-923
Lisovskii, I. P.-1223, 1223
Lobanov, G. P.-876
Lobanov, Yu. V.-837, 967
Loginov, A. S.-25
Logunov, V. N.-298
Loktionov, Yu. M.-343
Lomakin, S. S.-719
Lubanov, Yu. V.-502
Lukhminskii, B. E.-55
Lunina, L.1.-920
Lupakov, I. S.-14
L'vov, L. N.-88
Lyapidevskii, V. K.-1037
Lysikov, B. V.-893
Lyubchenko, V. F.-412
Maier, K.-431
Maiorov, L. A.-1240
Makarov, V. S.-1225
Maldinenko, L. A.-847
Makosov, V. V.-317
Maksimenko, B. P.-86
Mal'kov, V. V.-298, 1129
Malyshev, E. K.-208
Malyshev, I. F.-25
Marenkov, O. S.-627
Margulova, T. KI.-923
Martem'yanov, I. N.-1227
Martynova, 0.1.-776
Mashkovich, V. V.-1013
Maslov, A.1.-1003
Matora, I. M.-1012
Matusevich, E. S.-497, 1233
Matveenko, V. J.-452
Matyukhin, V. V.-925
Medvedev, Yu. A.-228
MePnikov, Yu. T.-317
Merkul' ev, Yu. A.-910
Merts, V.-431
Metelkin, A.1.-708
Michalev, R.-523
Mikhailov, G. A.-224
Millionshchikov, M. D.-268, 406, 696,
1178
Milovanov, 0. S.-850
Minashin, M. E.-412
Minenko, V.P.-1193
Mirnov, S. V.-160
Miroshnichenko, Yu. T.-1184
Mitin, A. A.-86
Mitov, V. N.-542
Mitropolskii, A. N.-1126
Mityaev, Yu. I.-412
Molin, G. A.-335, 637
Monoszon, N. A.-25
Mordashev, V. M.-214
Mordovskaya, T. S.-719
Moroz, E. M.-175, 177
Morozov, A. A.-1222
Morozov, V. A.-20
Morozov, V. M.-398
Morozova, I. K.-14
Moskalev, S. S.-150
Moskalev, Yu. 1.-593
Moskvin, L. N.-1236
Movsisyan, L. M.-651
Muminov, M.1,-722
Murin, A. N.-443
Myae, E. A.-998
Nalivaev, V. 1.-301, 302
Naskidashvili, I. A.-60, 418
Nasonova, G. I.-794
Nazarenko, N. G.-539
Nazarov, A.1.-776
Nazarov, I. M.-840
Nedumova, E. S.-56
Nelipovich, E. S.-820
Neshkov, D. Z.-228
Nesmeyanova, K. A.-781
1269
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Declassified and Approved For Release 2013/04/09: CIA-RDP10-02196R000700060001-1
Nestrelyaev, V. V.-1149
Neumann, Jan,-521
Nichipor, G. V.-763
Nichkov, I. F.-317
Nikitin, M. M.-1146
Nikolaev, B. L-1193
Nikolaev, N. M.-689
Nikolaev, V. A.-57, 1227
Nikolaev, V. L-832
Nosov, V. I.-64
Novak, V. E.-559
Novgorodtsev, R. B.-326
Novik-Kachan, V. P.-679
Novoselov, G. P.-51,52
Novozhilov, V. A.-1240
Nozik, V. Z.-910
Ochkur, A. P.-78, 542
Oganesyan, Yu. Ts.-967
Ogorodnik, S. S.-1221
Orlenko, N. I.-626
Orlov, Yu. V.-216
Osipov, V. V.-262, 820
Organesyan, Yu. Ts.-502
Orlov, V. V.-449
Ostanin, V. A.-850
Ostreikovskii, E. P.-372
Otgonsuren, 0.-1035
Ostrovskaya, G. Ya.-598
Ovander, L. N.-1133
Ovchinnikov, A. K.-739
Palei, P. N.-259
Panfilov, G. G.-719
Panasenkov, A. F.-425
Panteleev, L. D.-418
Papirov, 1.1,-195
Paramonova, I. N.-938
Pashkin, Yu. G.-184
Pasyuk, A. S.-91, 534
Pavlichenko, 0. S.-156
Pavlov, S. Yu.-328
Pavlov, Yu. F.-708
Pavlovskii, A.1.-549
Pavlov-Verevkin, B. S.-81
Penionzhkevich, Yu. E.-990
Perel' man, A. I.-2
Perelygin, V. P.-1035
Perevalov, V. G.-336
Pergamenshchik, V. K.-336
Petrenko, A. A.-1126
Petros 'yants , A. M.-372
Petrov, V.1.-719
Petrov, Yu. G.-460
1270
Petrov, Yu. N.-547
Petrova, T. I.-776
Petrzhak, K. A.-460
Petushkova, N. A.-1116
Pichugin, A. V.-300
Pikalov, G. L.-1113
Pikel'ner, L. B.-464
Pinkhasik, M. S.-1126
Piskun, A. S.-446
Pletenets, S. 5.-20
Plis, Yu. A.-822
Plotko, V. M.-502, 967
Plotnikov, R. I.-78
Polivanskii, V. P.-497
Polosukhina, K. N.-683
Poluboyarinov, Yu. V.-502
Polukhin, A. T.-1095
Polyanin, L. N.-935
Ponomarev-Stepnoi, N. N.-64,
1116
Popeko, L. A.-210
Popkovich, A. V.-25
Popov, V.1.-532
Posel'skii, N. N.-809
Posokhin, Yu. V.-530
Postnikov, V. V.-412, 920, 1067
Potapenko, V. A.-156
Potap'eva, L.E.-819
Potetyunko, G. N.-824, 1149
Pozdneev, D. B.-300
Preobrazhenskaya, L. B.-56
Prikot, K. N.-623
Primenko, G.1.-320, 323
Prisnyakov, V. F.-732
Pronman, I. M.-320, 323
Prokopchik, V.1.-737
Prudnikov, I. A.-918
Prusakov, V. N.-629
Prutkina, M.1.-724
Pshenichnyi, G. A.-78, 627
Pupko, V. Ya.-50, 497
Pushlenkov, M. F.-312
Pyatnov, E. G.-850
Pyzhova, Z.1.-259
Radchenko, S. V.-528
Raetskii, V. M.-773, 1131
Rambush, K.-431
Raspopin, S. P.-317, 1011
Ratnikov, E. F.-769
Rauzen, F. V.-703, 798
Regushevskii, V.1.-497
Repalov, N. S.-654
Rezvanov, R. A.-55
Roginskii, L. A.-178, 1224
Romanov, Yu. F.-460
Ronzhin, 0. B.-181
Roslik, S. F.-298
Rozhdestvenskii, B.V.-25
Rubtsov, K. S.-847
Rudakov, V. A.-156
Rumyantsev, G. Ya.-69
Runov, I. V.-559
Rybakova, G. D.-708
Ryabka, P. M.-847
Sabelev, G. L-533
Sabin, M. V.-938
Sachkov, V. F.-1227
Safronov, B. G.-654
Sakharov, E. S.-727, 826
Sakhnovskii, E. G.-911
Sakovich, V. A.-226
Saks aganskii, G. L.-25
Samoilov, P. S.-210, 719
Samoilov, Yu. F.-776
Samsonov, B. V.-876
Sarantsev, V. P.-1245
Sarkisov, A. A.-1227
Sazonova, E. V.-721
Sebko, V. P.-343
Selivanov, Yu. F.-9
Semenov, I. B.-160
Senatorov, G. F.-1224, 1248
Senin, M. D.-314
Serebrennikov, Yu. M.-1029, 1067
Serenkov, V.I.-1037
Sergachev, A. 1.-835
Severgin, Yu. P.-809
Shabelrnikov, L. A.-25
Shafranov, V. D.-801
Shamov, V. P.-593
Shamovskii, V. G.-1100
Shamsutdinov, A. 0.-990
Sharapov, V. N.-412
Shaskin, V. L.-724
Shatalov, V. V.-491
Shchedrin, I. S.-850
Shchepetilinikov, N. N.-312
Shchetinin, 0.1.-208
Sheglovskii, Z.-990
Shembel' , B. K.-820
Shenderovich, A. M.-554
Shifrin, I. G.-708
Shikov, S. B.-534
Shimanskaya, N. S.-457
Shimmel, V. V.-431
Shishin, B. P.-932
Shlyamin, E. A.-297, 460
Sholokhov, A. A.-683
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ShoPts , V.-431
Shpirkauskaite, N. K.-843
Shramenko. B. 1.-648
Shtivell man, A. Ya.-298
Shukeilo, I. A.-559
Shulepin, V. S.-67, 69,452
Shulimov, V. N.-876
Shuvalov, V. M.-412
Sidorin, V. P.-643, 1115
Sidorov, S. K.-537, 786
Sidorov, V.1.-533
Sidorin, V. P.-557
Sinel'nikov, K. D.-25
Sivintsev, Yu. V.-593
Skiba, 0. V.-171
Skibenko, A. 1.-1003
Skorikov, A. G.-727
Skorov, D. M.-941
Skorovarov, D. I.-491
Skvortsov, S. A.-380
Slavyanov, V. I.-1240
Smakhtin, L. A.-1223, 1223
Smirenkin, G. N.-532, 1190
Smirenkina, L. D.-835
Smirnov, I. A.-850
Smirnov, M. V.-530
Smirnov, 0. N.-1121
Snitko, E. I.-412, 1067
Sobenin, N. P.-850
Sobolev, A. V.-1227
Sofienko, L. A.-721
Sokolov, Yu. A.-25
Sokolova, Z. Ya.-205
Solov'ev, S. P.-326
Solov' eva, Z.1.-462
Sorokin, D. N.-192, 603, 730
Sorokina, A. V.-462
Soroko, L.M.-822
Spiridonov, A. I.-1137
Sprygaev, I. F.-1240
Stanolov, A.-1010
Starizhyi, E.S.-331, 624
Stavisskii, Yu. Ya.-497
Stavitskii, R. V.-1112
Stapanov, A. V.-1119
Stepanov, B.M.-228
Sterman, L. S.-1124
Stoyanov, Ch.-914
Strakhov, I. P.-708
Strizhak, V.1.-320, 323
Stumbur, E.A.-449, 928
Styro, B. I.-843
Subbotin, V.I.-9, 20, 192, 603,
620, 730, 925
Sudakova, N. V.-198
Sukhanova, K.A.-299
Sulaberidze, G.A.-832, 1193
Sulygin, I. I.-820
Suprunenko, V. A.-25
Susloparov, M. S.-918
Sviridenko, E. Ya.-620
Sviridenko, V. E.-9
Sychev, B.S.-1129
Taliev, A. V.-718
Talyzin, V. V.-722
Tananakin, V. A.-549
Tarantin, N. I.-821
Tarantin, V. D.-1126
Teplyakov, V.A.-645
Terent'ev, V. P.-986
Tereshchenko, F. F.-156
Terman, A. V.-593
Teteltbaum, S. D.-976
Teverovskii, E. N.-593
Tikhinskii, G. F.-195
Timchenko, R. A.-876
Timofeeva, T. V.-739
Tishin, A.S.-532
Tolok, V. T.-25, 156
Tolstoluzhskii, A. P.-631
Tonopetian, S. G.-648
Toropov, A.S.-918
TreVyak, S. A.-832, 1193
Tretiyakov, Yu. P.-91
Tretlyakova, S. P.-502, 967
Troshin, V.S.-719
Troyanov, E.F.-998
Trushkov, N. D.-798
Try'yakov, Yu. P.-534
Tsoglin, Yu. L.-1221
Tsukerman, I. Kh.-1126
Tsyganok, A. A.-603
Tsykanov, V.A.-623, 876, 882
Tustanovskii, V. T.-818
Tyminskii, V. G.-1137
Ushakov, P.A.-620
Uspenskii, V. K.-623
Ustinov, A.A.-57
Usynin, G.B.-935
Utkin, V.1.-720
V
Vagapov, R. Kh.-641
Vagin, Yu. P.-228
Val'dner, 0. A.-850
Vasilenko, B.T.-156
Vas il' ev , G. Ya.-454
Vasil'ev, S.S.-76
Vasinov, V. G.-858
Vatulin, V.V.-815
Vavilov, V.S.-641
Vavra, J.-523
Vazinger, V. V.-911
Vedishcheva, T. S.-703
Velyus, L.M.-76
Venikov, N. I.-809
Vertebnyi, V. P.-186
Vetyukov, V.N.-920
Viktorov, A.-1013
Vikulov, V.K.-412
Viselkina, M. A.-2
Vladimirov, L. A.-1140
Vladimirova, M. V.-544
Vlasov, A. D.-282, 852
Voinov, E.M.-976
Voligemut, A. A.-818
Volgin, V. I.-1223
Volkov, E.D.-156
Volkovich, A. V.-1011
Voloshchuk, A. I.-886, 1184
Vorobei, M.P.-171
Vorob'ev, A.A.-339, 1146
Vorob'ev, E.D.-91
Vorob'ev, M. A.-135
Vorob'ev, V.A.-840
Vorob'eva, V. G.-835
Vorotnikov, P. E.-735
Votinov, S.N.-882
Vozzhenikov, G. S.-173
Yakovlev, G.N.-312
Yanshevskii, Yu. P.-542
Yarkovoi, E. A.-1112
Yudin, F. P.-1140
Yudkevich, M.S.-910
Yuferev, V.1.-815
Yuferov, V. B.-1003
Yurchenko, E. L-801
Yur'ev, Yu. S.-497
Yuzgin, V.S.-328
Zagorets, P. A.-1240
Zaikin, Yu. I.-1016
Zaitsev, L.N.-1115
Zaitsev, R. Ya.-301, 302
Zamyatnin, Yu. S.-790, 938
Zaslavskii, V. G.-443
Zatserkovskii, R. A.-186
Zavgorodnii, A. Ya.-1131
Zelenova, 0. I.-2
Zelenskii, V. F.-886, 1184
Zel' venskii, Ya. D.-56
1271
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Zenkevich, V.S.-150
Zenkov, D.I.-549
Zharkov, G.M.-986
Zharkov, V.P.-216
1272
Zhukov, A. V.-620
Zhuravlev, A. A.-163
ZiPberman, M. I.-722
ZoPnikov, P.P.-299
Zolotukhin, V. G.-1013
Zotov, A. V.-643
Zotov, V.S.-941
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TABLES OF CONTENTS
SOVIET ATOMIC ENERGY
Volumes 28-29, 1970
(A translation of Atomnaya nergiya)
Volume 28, Number 1 January, 1970
Engl./Russ.
1969 Recipients of USSR State Prizes
1
2
Two Classes of Geochemical Reducing Barriers in Exogenous Uranium Deposits
?0. I. Zelenova, M. A. Viselkina, and A. I. Perel'man
2
Investigation of the Dynamics of Vapor Bubbles in Boiling of Water in Thin Shells
under Natural Convection ? V. I. Subbotin, S. P. Kaznovskii, S. K. Korotaev,
V. E. Sviridenko, and Yu. F. Selivanov
9
Corrosion and Electrochemical Behavior of Carbon Steels in Quasi-Reactor Conditions
? V. V. Gerasimov, A. I. Gromova, I. S. Lupakov, I. K. Morozova,
A. A. Bakulevskii, V. N. Belous, and B. I. Kolesov
14
13
Solubility of Gases in a Eutectic Alloy of Sodium and Potassium ? M. N. Arnol'dov,
M. N. Ivanovskii, V. A. Morozov, S. S. Pletenets, and V. I. Subbotin
20
18
Uragan Experimental Thermonuclear Equipment ? V. F. Aleksin, 0. V. Biryukov,
A. V. Georgievskii, L. Kh. Kitaevskii, E. G. Komar, A. S. Loginov,
I. F. Malyshev, N. A. Monoszon, A. V. Popkovich, B. V. Rozhdestvenskii,
G. L. Saksaganskii, K. D. Sinel'nikov, Yu. A. Sokolov, V. A. Suprunenko,
V. T. Tolok, G. F. Churakov, and L. A. Shabel'nikov
25
22
Gas Desorption during Proton Irradiation of Metals and Metal ?Metallic Film Systems
? M. P. Katrich, L. N. Kalashnikov, and N. A. Kosik
31
28
REVIEWS
Present State and Design Trends of Thermionic Converters ? Yu. I. Danilov
and D. V. Karetnikov
36
33
New Data on Neutron Spectroscopy of Heavy Nuclei ? S. I. Sukhoruchkin
41
38
ABSTRACTS
Optimization of Fuel Breeding in Reactors ? V. I. Kuemin and V. Ya. Pupko
50
47
Interaction of Uranium and Its Alloys with Alkali Metal Fluorides ? G. P. Novoselov,
I. N. Kashcheev, and Yu. D. Dogaev
51
48
Extraction of Plutonium by Fluoride Melts ? G. P. Novoselov, I. N. Kashcheev,
and Yu. D. Dogaev
52
49
Solution of the Transport Equation by the Method of Characteristics ? L. P. Bass
53
49
Reconstruction of the Spectral and Angular-Distribution Function of Sources of
y-Quanta Radiation ? S. A. Churin
54
50
Monte Carlo Calculation of Nonstationary Distributions of Neutrons and Capture
y-Rays in Nuclear. Geophysics Problems ? V. Ya. Gommershtadt,
S. A. Denisik, B. E. Lukhminskii, and R. A. Rezvanov
55
51
Oxygen Isotope Separation Factor at Equilibrium of Water Vapor with Basic Aqueous
Solutions ? L. B. Preobrazhenskaya, E. S. Nedumova, and Ya. D. Zel'venskii,
56
51
LETTERS TO THE EDITOR
Certain Experimental Neutron ?Physical Characteristics of the SO-1 Breeder
? L. V. Konstantinov, V. A. Nikolaev, A. I. Efanov, and A. A. Ustinov
57
53
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Tensile-Testing Device for Micro-Scale Specimens in a Reactor Low-Temperature
Channel - I. A. Naskidashvili, E. S. Lapiashvili, A. N. Lezhava,
Engl./Russ.
and Dzh. G. Katsitadze
60
55
Fltix Mapping in Heterogeneous Reactors by Spacing of Blocks - N. N. Ponomarev-
Stepnoi, E. S. Glushkov, V. I. Nosov, and S. N. Barkov
64
58
Calculation of Reactor Criticality in the Asymptotic Approximation - V. S. Shulepin . .
67
60
Calculation of Reactor Criticality by Solving a System of Nonlinear Equations
- V. S. Shulepin and G. Ya. Rumyantsev
69
61'
Sublimation of Americium Tetrafluoride - E. G. Chudinov and D. Ya. Choporov
71
62
Separation and Purification of Gallium Isotopes by an Extraction -Chromatographic
Method - I. K. Ad'yasevich and E. P. Berskaya
74
64
Analysis of Isotopic Composition of Europium and Iridium by Thermal Neutron
Absorption - S. S. Vasirev, L. M. Velyus, P. D. Korzh, and V. T. Fomenko
76
65
Applications of Radioisotope X-Ray Luminescent Analysis to Determination of the Real
Composition of Rocks and Ores in Motion - G. A. Pshenichnyi, A. P. Ochkur,
R. I. Plotnikov, and D. A. Goganov
78
67
Deactivation of Radioactive Waste from Fe55 Production - B. S. Pavlov-Verevkin
81
69
Underground Burial of Harmful Wastes - P. F. Dolgikh and V. G. Bakhurov
83
70
Electron Detection by Silicon Surface-Barrier Counters on y-Background of
Comparable Energy B. P. Maksimenko, V. N. Bezmel 'nitsyn, and A. A. Mitin
86
71
Distribution of Fragments from Spontaneous Fission of CM244, from Track Diameters
on the Surface of Silicate Glass - V. K. Gorshkov, L. N. L'vov, and
and G. A. Khrudeva
88
73
Source of Multiply Charged Calcium and Zinc Ions - A. S. Pasyuk, E. D. Vorob'ev,
R. I. Ivannikov, V. I. Kuznetsov, V. B. Kutner, and Yu. P. Tret 'yakov
91
75
CHRONICLES
Aleksandr L'vovich Mints. On the Occasion of His Seventy-Fifth Birthday
95
79
Vladimir Ivanovich Smirnov. On the Occasion of His Sixtieth Birthday
98
81
NEWS OF SCIENCE AND TECHNOLOGY
Symposium on Radiation Damage in Reactor Materials - P. A. Platonov
101
83
Conference on Nuclear Reactions Caused by Heavy Ions, Heidelberg, July, 1969
104
85
Second Symposium on the Physics and Chemistry of Fission (IAEA, Summer, 1969)
- S. A. Karamyan and Yu. V. Ryabov
107
87
Conference on the Chemistry of Solvent Extraction - G. A. Yagodin
111
89
IAEA Conference on Information on Nuclear Power Facilities - Yu. V. Arkhangerskii
114
90
The Uranium Industry in the Capitalist and Developing Countries in 1968
-V. D. Andreev
116
91
Nuclear Resqarch Centers in Belgium and the Netherlands - V. I. Man'ko
129
99
BRIEF COMMUNICATIONS
132
101
-Volume 28, Number 2 February, 1970
Mechanical Properties of Irradiated Uranium - M. A. Vorob,ev, Yu. M. Golovchenko,
A. S. Davydenko and B. A. Bychkov
135
107
Neutron-Irradiation Method for Analyzing Fissionable Substances - V. K. Begatyrev,
B. G. Dubovskii, and V. V. Frolov
140
111
Use of a Germanium Detector for a Neutron-Radiation Analysis of the Content of Elements
and Isotopes - A. M. Demidov, L. I. Govor, and V. A. Ivanov
145
115
Neutron Spectrometer for Measuring Scattering Cross Sections by the Time-of-Flight
Method - V. F. Gerasimov, V. S. Zenkevich, and S. S. Moskalev
150
120
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Engl./Russ.
On the Mechanism of Plasma Loss in the Stellarator ? P. Ya. Burchenko,
B. T. Vasilenko, E. D. Volkov, 0. S. Pavlichenko, V. A. Potapenko,
V. A. Rudakov, F. F. Tereshchenko, and V. T. Tolok
Measurement of Ion Temperature in the "Tokamak T-3" Facility from Doppler
Broadening of Spectral Lines of Neutral Hydrogen and Deuterium ? S. V. Mirnov
and I. B. Semenov
Some Results of the All-Round Alignment and Startup of the 70 GeV Proton Synchrotron
at the Institute of High Energy Physics ? Yu. M. Ado, A. A. Zhuravlev,
A. A. Logunov, E. A. Myaz, A. A. Naumov, V. E. Pisarevskii,
V. G. Rogozinskii, K. Z. Tushabramishvili, I. A. Shukeilo, S. N. Boiko,
E. G. Komar, I. F. Malyshev, I. V. Mozin, N. A. Monoszon, I. A. Mozalevskii,
F. M. Spevakova, A. M. Stolov, V. A. Titov, F. A. Vodop'yanov, A. A. Kuz'min,
V. F. Kuztmin, A. L. Mints, S. M. Rubchinskii, V. A. Uvarov, B. M. Gutner,
V. B. Zalmanzon, A. I. Prokoptev, and A. S. Temkin
ABSTRACTS
Investigation of Salt Systems Based on LiC1, RbC1, CsCI, and UO2C12 ? M. P. Vorobei,
0. V. Sldba, and A. S. Bevz
Calibration of Direct-Charging Detectors for Measurement of Absolute Thermal-Neutron
Flux ? A. E. Alekseev, E. N. Babulevich, L. A. Goncharev, V. A. Zagadkin,
V. S. Kirsanov, A. A. Kononovich, V. M. Kuznetsov, E. M. Kuznetsov,
M. G. Miteltman, G. P. Pochivalin, and N. D. Rozenblyum
Gamma Intensity of the Induced Activity in Coal Seams of Finite Thickness
? G. S. Vozzhenikov
Parameters Determining the Gamma Distribution in a Medium of Arbitrary Elemental?
Composition ? I. M. Khaikovich
On the Possibility of Suppressing Helical Modes of Hydromagnetic Instability of a Plasma
Filament with Current by a System of Feed Backs ? V. V. Arsenin
Geometry of the Orbits in Sector-Type Cyclotrons ? E. M. Moroz
Method of Calculating the Ion Trajectories in a Radial-Sector Step-Field Cyclotron
? E. M. Moroz
Stabilization of the Transverse Coherent Resistance Instability by Automatic Correction
? L . A. Roginskii
LETTERS TO THE EDITOR
Gas Evolution in the First Loop of a Water-Cooled, Water-Moderated Reactor with Gas
Volume Compensators ? N. V. Bychkov and A. I. Kasperovich
Estimate of the Asymptotic Stability Region in Thermal Reactors with Discrete Control
Systems ? 0. B. Ronzhin
Accuracy of the Wigner Approximation ? Yu. G. Pashkin
Absolute Measurements of Integrated Dosages of Slow Neutrons in the Active Zone of an
Atomic Reactor, Using a Transmission Method ? V. P. Vertebnyi,
R. A. Zatserkovskii, and A. L. Kirilyuk
Volatility of Plutonium Tetrafluoride ? E. G. Chudinov and D. Ya. Choporov
Superheating Values Required for the Boiling of Alkali Metals ? V. I. Subbotin,
D. N. Sorokin, and A. P. Kudryaystsev
Properties of Irradiated Beryllium ? L. A. Kornienko, I. I. Papirov,
G. F. Tikhinskii, and A. S. Davidenko
Gaseous Swelling in Irradiated Beryllium Oxide ? A. V. Khudyakov, N. V. Sudakova,
and G. S. Balandin
Neutrons with Energies Less than 1 MeV in Spectra from Be (a, N) Sources
? V. I. Fominyldi
Parameters of ZnS(Ag) Scintillators for Neutron Recording ? Z. Ya. Sokolova and
V. B. Chernyaev
156
126
160
129
163
132
171
139
172
139
173
140
174
140
175
141
175
142
177
143
178
143
180
145
181
145
184
147
186
149
189
151
192
153
195
155
198
157
201
159
205
162
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Three-Component Isotopic Mixture for Neutron Measurements in Fission Chambers
Engl./Russ.
? 0. I. Shchetinin, A. V. Dmitriev, and E. K. Malyshev
208
164
Ge (Li) Spectrometer with Thermoelectric Cooler ? I. N. Arsenttev, I. S. Denprovskii,
L. A. Popeko, and P. S. Samoilov
210
165
Neutron Scattering in Air ? V. M. Mordashev
214
168
Back Scattering of Neutrons from Aluminum, Titanium, Graphite, and Polyethylene
? Yu. A. Egorov, V. P. Zharkov, and Yu. V. Orlov
216
170
Photoabsorption Coefficients and Effective Atomic Number of Elements and Complex
Media for Low-Energy Gamma Rays ? E. P. Leman
219
172
Statistical Spread in Ranges of Heavy. Charged Particles ? V. S. Kessellman and
Yu. V. Bulgakov
221
173
A Method for Simulating the Mean Free Path of a Particle ? G. A. Mikhailov
224
175
Optimization of the Shape of a Shadow Shield by the Monte ? Carlo Method
? V. L. Generozov and V. A. Sakovich
226
175
Luminescence of Air Bombarded by Fast Electrons ? Yu. P. Vagin, G. L. Kabanov,
Yu. A. Medvedev, D. Z. Neshkov, and B. M. Stepanov
228
177
NEWS
BOR-60 Reactor now in Operation ? E. P. Karelin and B. N. Koverdyaev
231
179
Science and Engineering Conference on Nucleonic Instrumentation ? N. A. Shekhovtsov
234
181
Leaching of Radioactive Isotopes from Solids ? V. V. Kulichenko
235
182
VIII International Congress and General Assembly of the International Union of
Crystallography ? M. G. Zemlyanov
237
183
III International Conference on Collision of High-Energy Particles, and III International
Conference on High-Energy Physics and Structure of the Nucleus
? A. A. Kuznetsov
239
184
International Conference on the Properties of Nuclear States ? V. G. Solovlev and
N. I. Pyatov
242
186
International Conference on Interactions of Electrons and Protons at High Energies
? L. D. Solovtev
244
187
International School on the Physics of Elementary Particles ? V. S. Kaftanov
247
189
Symposium on Analytical Chemistry ? V. A. Khalkin
249
189
Production of Isotopes in the Comecon Countries
252
191
BRIEF COMMUNICATIONS
254
192
BOOK REVIEWS
B. N. Sudarikov and E. G. Rakov ? Processes and Equipment in Uranium Production
? Reviewed by A. Pushkov
256
193
Steam Generating and Other Heavy Water Reactors
256
193
A. Klusmann and H. Volcker ? Nuclear Reactor Fuel Elements
258
194
Volume 28, Number 3 March, 1970
Investigation of the Buildup of Isotopes of Protoactinium and Uranium when Th23? and
Th232 Are Irradiated by Thermal Neutrons ? Z. K. Karalova, P. N. Palei,
R. N. Ivanov, V. Ya. Gabeskiriya, and Z. I. Pyzhova
259
199
Intermetallic Compounds of Zirconium and Their Influence on the Corrosion Properties
of Zirconium Alloys ? A. I. Evstyukhin, I. I. Korobkov, and V. V. Osipov
262
201
Turbulent Flow in the Boundary Layer and in Tubes ? M. D. Millionshchikov
268
207
Limiting Current during Neutral Initial Equilibrium of Clusters in a Linear Accelerator
?A. D. Vlasov
282
220
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REVIEWS
The Development of Views on Radiation Protection Standards ? A. A. Letavet,
Engl./Russ.
I. K. Dibobes, E. N. Teverovskii, and A. V. Terman
287
225
International Nuclear Information System ? I. D. Morokhov, V. F. Semenov,
L.L. Isaev, M. V. Ivanov, and I. V. Tikhonov
294
231
ABSTRACTS
Peculiarities of the Production of Th228 and U232 by Neutron Irradiation of Pam
?M. A. Bak, Yu. I. Baranov, A. S. Krivokhatskii, and P. A. Shlyamin
297
234
Calculation of the Yield of Secondary Neutrons in the Interaction of Accelerated
Electrons with Matter ? V. N. Logunov, V. V. MaPkov, S. F. Roslik, and
A. Ya. Shtiverman
298
235
Albedo of Bremsstrahlung -y-Radiation ? P. P. Zol'nikov, B. L. Dvinyaninov, and
K. A. Sukhanova
299
235
Spectral and Angular Distributions of Backscattered Cs137 -y-Rays Emerging from
Various Parts of a Reflector ? A. V. Pichugin and D. B. Pozdneev
300
236
Angular Distribution of Monoenergetic Electrons and Beta Particles Scattered in a
Shield ?V. F. Baranov, N. P. Bondarenko, L. I. Burmagin, R. Ya. Zaitsev,
V. V. Kudinov, and V. I. Nalivaev
301
237
An Adsorption Method for Determining the Energy Distribution of Electrons Incident
on and Transmitted through a Shield ? V. F. Baranov, R. Ya. Zaitsev, and
V. I. Nalivaev
302
237
Calculation of Self-Absorption in '3-Sources ? A. A. Belyaev and A. I. Krupman
303
238
LETTERS TO THE EDITOR
Effectiveness of Using Steam Power Evaporating Equipment in Atomic Electric Power
Plant ?A. F. Dvornikov
304
239
Detection of Hydrogen in a Sodium Heat Exchanger ? V. S. Kopylov, M. N. Korotaeva,
and g. E. Konovalov
307
241
Distribution of Thermal Neutrons in a Cylindrical Cell ? N. I. Laletin
309
242
A Miniature Centrifugal Extractor ? G. N. Yakovlev, M. F. Pushlenkov,
N. N. Shchepetil'nikov, and A. P. Feofanov
312
244
Enthalpy of BeH2 Formation ? V. V. Akhachinskii, L. M. Kopytin, and M. D. Senin
314
245
The Fusibilities of Salt Systems Containing Uranium Trichloride ? V. N. Desyatnik,
Yu. T. Mel'nikov, I. F. Nichkov, S. P. Raspopin, and V. V. Makosov
317
247
Tritium-Filled Targets of Scandium, Yttrium, Praseodymium, Neodymium, and
Erbium ? V. I. Strizhak, G. I. Primenko, V. I. Katsaurov, and I. M. Pronman
320
249
Preparation and Investigation of Injected Targets for the Reaction T (d,n)
? V. I. Strizhak, G. I. Primenko, and I. M. Pronman
323
251
Measurement of a Flux of Slow Neutrons by Means of the Hall Effect in Silicon
? V. A. Kharchenko, S. P. Solov'ev, and R. B. Novgorodtsev
326
253
Efficiency of a Body-Radiation Spectrometer when There is a Nonuniform Isotopic
Distribution in the Source ? S. Yu. Pavlov and V. S. Yuzgin
328
254
Two Methods for Reducing the Nonuniformity of the Dose Field along the Source in a
Radiation Loop ? E. S. Stariznyi and A. Kb. Breger
331
255
Yield of F18 in the Bombardment of Sodium, Magnesium, and Aluminum by Hes Ions and
Sodium by a-Particles ? N. N. Krasnov, P. P. Dmitriev, Z. P. Dmitrieva,
I. 0. Konstantinov, and G. A. Molin
333
257
C11 Yield in the Reactions BO (Hes, n) C11 and Be8 (a, 2n) C11 ? N. N. Krasnov,
P. P. Dmitriev, Z. P. Dmitrieva, I. 0. Konstantinov, and G. A. Molin
335
258
Hematite Concrete for Shielding against High Neutron Fluxes ? V. B. Dubrovskii,
Sh. Sh. Ibragimov, V. V. Korenevskii, A. Ya. Ladygin, V. K. Pergamenshchik,
and V. S. Perevalov
336
258
1277
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Experimental Investigation of the Dynamics of an Electron Beam in a Synchrotron at 1.5
Engl./Russ.
GeV ?A. A. Vorob'ev, A. N. Didenko, and A. V. Kozhevnikov
339
260
Operation of Stellarator Circularizers in the Presence of an Axial Current
? Yu. M. Loktionov and V. P. Sebko
343
263
NEWS
Startup of the Second Reactor Unit in the Novo-Voronezh' Nuclear Power Station
?Yu. Arkhangel'skii
346
266
First Row of the Belyi Yar Nuclear Power Station Brought up to Design Power
347
266
Cost Aspects of Nuclear Power ? V. V. Batov
349
267
Seminar on Diffusional Saturation and Diffusion Coatings ? A. L. Burykina
352
269
Isochronous Cyclotrons and Their Applications in Chemistry, Metallurgy, and Biology
? N. I. Venikov and B. N. Yablokov
354
270
XVIIth Session of the COMECON Commission on Peaceful Uses of Atomic Energy
365
280
International Conference (Kyoto, Japan) on Mass Spectrometry
368
282
Volume 28, Number 4 April, 1970
From the Editor
371
286
The Nuclear Research Center at the Birthplace of V. I. Lenin ?0. D. Kazachkovskii,
N. V. Krasnoyarov, E. P. Ostreikovskii, and A. M. Petros'yants
372
287
Special Features of Nuclear Power Stations in Energy Generation ? E. P. Anan'ev
and G. N. Kruzhilin
376
291
Prospects of Water-Moderated Water-Cooled Power Reactors ? S. A. Skvortsov
380
294
Present State and Future Prospects of Fast Reactions ?A. I. Leipunskii
384
297
Synthesis and Search for Heavy Transuranium Elements ?G. N. Flerov
390
302
On the Anomalous Scattering of Neutrons ?N. S. Lebedeva and V. M. Morozov
398
310
The Basic Laws of Turbulent Flow ? M. D. Millionshchikov
406
317
Investigation of Critical Assemblies of the Beloyarsk Nuclear Power Station
? I. S. Akimov, V. I. Alekseev, V. K. Vikulov, B. G. Dubovskii, A. Ya, Evseev,
I. M. Kisili , L. V. Konstantinov, V. F. Lyubchenko, M. E. Minashin,
Yu. I. Mityaev, V. V. Postnikov, E. I. Snitko, V. N. Sharapov, and V. M. Shuvalov
412
321
Radiative Growth of Uranium at Small Burnups ? S. T. Konobeevskii, L. D. Panteleev,
B. M. Levitskii, and I. A. Naskidashvili
418
326
Fruitful Collaboration for Peace and Progress ?A. F. Panasenkov
425
332
The Use of Nuclear Energy in the German Democratic Republic ?Kh. FauPshtikh,
L. Kherfort, V. Merts, K. Maier, K. Rambush, V. V. Shimmelt, and V. Sholtts .
431
338
ARTICLES FROM HUNGARY
The Nuclear Reactor of the Polytechnic Institute in Budapest ?D. Csom
435
342
Reprocessing of Biological Radioactive Wastes in the Hungarian People's Republic
? L. Feller and F. Gacs
440
346
LETTERS TO THE EDITOR
Isotopic Abundance of Lithium in Uranium Minerals ?L. K. Levskii, A. N. Murin,
and V. G. Zaslavskii
443
349
Swelling of Hot Oxide Fuel ? I. T. Lebedev, V. I. Kuz'min, and A. S. Piskun
446
351
The Physical Interpretation of the Theorem of the Reactivity Integral ?V. V. Orlov
and A. A. Stumbur
449
353
Determining the Reactivity Margin ?V. S. Shulepin and V. I. Matveenko
452
355
Entrainment of Neutrons by a Moving Medium ?G. Ya. Vasil'ev, D. M. Kaminker,
K. A. Konoplev, and A. A. Kostritsa
454
356
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Measurement of the Parameters of the Neutron Flux in a Reaction by Means of
Activation Coincidence Counters -E. I. Biryukov, N. N. Khramov,
Engl./Russ.
and N. S. Shimanskaya
457
357
Resonance Fission Integrals for Uranium, Plutonium, and Americium Isotopes
-M. A. Bak, K. A. Petrzhak, Yu. G. Petrov, Yu. F. Romanov, and
E. A. Shlyamin
460
359
On the Spontaneous Fission Half-Life of ,C1252 - B. M. Aleksandrov, M. A. Bak,
V. G. Bogdanov, S. S. Bugorkov, L. V. Drapchinskii, Z. I. Solov'eva, and
A. V. Sorokina
462
361
The Cross Section for Fission of Np237 by Slow Neutrons -K. A. Gavrilov,
K. K. Koshaeva, S. N. Kraitor, and L. B. Pikel'ner
464
362
NEWS
Truck-Mounted IfKolos? Full-Scale '-Irradiator Facility ? D. A. Kaushanskii
and B. G. Zhukov
468
366
"fir Thermoelectric Radioisotope Facility - G. M. Fradkin, A. I. Ragozinskii,
and A. I. Dmitriev
470
367
RTR-1 Scintillation Type Radioisotope Relay Device - I. I. Kreindlin and Yu. A. Skoblo
472
369
Radioisotope Apparatus for Internal Irradiation -A. G. SulTkin
474
370
Set of Equipment for the Radiological Division of a Hospital -G. I. Lukishov,
K. D. Rodionov, and Yu. A. Sokolov
475
370
Budapest October, 1969,Symposium on Monitoring and Control of Nuclear Reactions and
Power Station Equipment -A. G. Filippov
478
372
Radiation Safety in the Design and Use of Hot Laboratories -V. N. Kosyakov
482
375
International Conference on Plasma Confinement in Closed Systems -V. S. Strelkov
and I. S. Shpigel'
485
377
Emission of Radioactive Noble Gases during the Regeneration of Nuclear Fuel
-A. D. Turkin
489
379
Volume 28, Number 5 May, 1970
Basic Principles in the Extraction of Uranium by Phosphine Oxide - B. N. Laskorin,
D. I. Skorovarov, L. A. Fedorova, and V. V. Shatalov
491
383
Physical Investigations of an Electronuclear Neutron-Flux-Generator Target
- V. I. Boltshov, A. A. Dubinin, V. M. Dmitriev, S. P. Kapchigashev,
V. A. Kon'shin, E. S. Matusevich, V. P. Polivanskii, V. Ya. Pupko,
V. I. Regushevskii, Yu. Ya. Stavisskii, and Yu. S. Yurtev
497
388
Identification of the Elements 102 and 104 by Means of the Collimation Method
- Yu. Ts. Organesyan, Yu. V. Lobanov, S. P. Trettyakova, Yu. A. Lazarev,
I. V. Kolesov, K. A. Gavrilov, V. M. Plotko, and Yu. V. Poluboyarinov
502
393
Radiation Sputtering and Damage of Certain Metals in the Radiation Field of a Nuclear
Reactor. Part I. Sputtering by Fast Neutrons - R. I. Garber, V. S. Karasev,
V. M. Kolyada, and A. I. Fedorenko
510
400
Radiation Sputtering and Damage to Certain Metals in the Radiation Field of a Nuclear
Reactor. Part 2. Sputtering by Fission Fragments from U235 and Reactor
Neutrons - R. I. Garber, V. S. Karasev, V. M. Kolyada,and A. I. Fedorenko
516
406
ARTICLES FROM CZECHOSLOVAKIA
Collaboration between Czechoslovakia and the USSR in the Peaceful Use of Atomic
Energy - Jan Neumann
521
411
Study of Neutron Diffraction in the Institute of Nuclear Studies of the Czechoslovakian
Academy of Sciences - B. Chalupa, R. Michalec, and J. Vavra
523
413
1279
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ABSTRACTS
Multiparameter Optimization of an Atomic Power Plant with Base-Point Distillation
of Sea Water - Yu. D. Arsen'ev, S. V. Radchenko, and V. A. Chernyaev
Accumulation of Plutonium for the Development of Fast Reactors
- 0. D. Kazachkovskii and E. V. Kirillov
Electrochemical Behavior of Thorium in Molten Sodium Chloride and an Equimolar
Engl./Russ.
528 418
529 418
Mixture of Potassium and Sodium Chlorides - M. V. Smirnov, V. Ya. Kudyakov,
Yu. V. Posokhin, and Yu. N. Krasnov
530
419
Measurement of the Fast Neutron Distribution in a Cell of a Uranium- Graphite
Reactor with a Rhodium Threshold Detector - A. V. Bushuev, V. G. Bortsov,
and V. M. Duvanov
531
420
Optimum Parameters of the U238 Neutron Optical Potential - G. V. Anikin,
A. G. Dovbenko, L. Ya. Kazakova, V. E. Kolesov, V. I. Popov, G. N.
G. N. Smirenkin, and A. S. Tishin
532
420
Temperature Field in a Nonisothermal Two-Phase Flow - M. Kh. Ibragimov,
G. I. Sabelev, and V. I. Sidorov
533
421
Role of Energy Dependence in Problems of Transport Theory - Yu. I. Ershov
and S. B. Shikhov
534
422
Source of Multiply Charged Ions with Cathode Atomization of the Operating Substance
- Yu. P. Trt'yakov, A. S. Pasyuk, L. P. Kurkina, and V. I. Kuznetsov
534
423
Conditions for the Existence of Two Stable Equilibrium Phases in Linear Accelerators
- I. D. Dreval' and V. V. Kushin
536
423
LETTERS TO THE EDITOR
Characteristics of Spectra of Thermal Neutrons from Straight Tangential Channel of a
Reactor - B. I. Goschitskii, V. V. Gusev, L. V. Konstantinov,
P. M. Korotovskikh, S. K. Sidorov, V. V. Chernobrovkin, and V. G. Chudinov
537
425
Reduction of Compact U308 by Hydrogen - Yu. M. Dymkov, N. G. Nazarenko,
G. A. Dymkova, and E. F. Goryunov
539
426
Use of Semiconductor Detectors in Isotopic X-Ray Fluorescence Method
- A. A. Fedorov, A. P. Ochkur, V. N. Mitov, and Yu. P. Yanshevskii
542
428
New Chemical Method for Determining Dose Rate of Various Forms of Radiation
- M. V. Vladimirova and I. A. Kulikov
544
429
Observation and Identification of a Radioactive Cloud by a Very Simple Radiometric
Method - Yu. N. Petrov
547
431
An Iron-Free Linear Induction Accelerator - A. I. Pavlovskii, A. I. Gerasimov,
D. I. Zenkov, V. S. Bosamykin, A. P. Klement' ev, and V. A. Tananakin
549
432
Resonance Acceleration of a Beam of Oscillators in the Field of a Plane Wave
- V. B. Krasovitskii
551
434
On the Damping of Nonlinear Synchrotron Oscillations of Two Bunches during the
Interaction of a Beam with a Resonator - S. G. Kononenko and A. M. Shenderovich
554
436
Escape of Radiation from the Shield of the Joint Institute for Nuclear Research (JINR)
Synchrocyclotron - V. E. Aleinikov, L. R. Kimel', M. M. Komochkov,
and V. P. Sidorin
557
438
Deformations of the Foundation of the Serpukhov Accelerator and Their Effect on the
Shape of the Equilibrium Orbit - V. E. Novak, I. V. Runov, A. E. Khanamiryan,
and I. A. Shukeilo
559
439
NEWS
Scientific and Technical Progress
562
442
All-Union Young Scientists' Conference on Radiation Chemistry - I. V. Vershchinskii
564
443
C14 Variations in the Earth's Atmosphere - G. E. Kocharov
566
444
Anglo-Soviet Seminar at Harwell - E. P. Ryazantsev
569
446
Seminar on Nuclear Research Using Low-Energy and Medium-Energy Linear Electron
Accelerators --P. V. Sorokin
572
448
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Engl./ Russ.
Conference on Nuclear Data - A. N. Abramov, V. I. Popov, and S. I. Sukhoruchkin
International Congress on Transport of Fission Products - G.I. Pavlov
Nuclear Seminar of Leningrad State University (25th Anniversary) - M. A. Listengarten
Research on the Atomic Nucleus and on Cosmic Rays in India - N. A. Burgov
Cost Savings through the Use of "Kolos" y-Ray Production-Model Irradiators
- N. S. Prokof'ev, D. A. Kaushanskii, and B. G. Zhukov
"Start" Facility for Measuring and Grading Radioactive Ore - V. P. Bovin,
N. K. Dorofeev, and L. N. Posik
BRIEF COMMUNICATIONS
V. Dolinin
BOOK REVIEWS
V. V. Batov and Yu. I. Koryakin, Economics of Nuclear Power
- Reviewed by E. 0. Shteingauz
F. G. Krotov (editor) - Preventive Measures in Dealing with Radiation Sickness and
Radiation Injuries as a Public-Health Problem (Scientific Review, No. 1)
Neutron Cross Sections for Fast Reactor Materials. Part 1. Evaluation
R. E. Marshak, Riazudin, and C. P. Ryan - Theory of Weak Interactions in Particle
Physics
Radiobiology - Medical Radiology Handbook [in German]
C. D. Van Cleave - Late Somatic Effects of Ionizing Radiation
Volume 28, Number 6
Radiation Safety Standards (NRB-69) - I. K. Dibobes, V. A. Knyazev, A. A. Moiseev,
Yu. I. Moskalev, Yu. V. Sivintsev, E. N. Teverovskii, A. V. Terman, and
V. P. Shamov
Uranium in Carboniferous Rocks - G. Ya. Ostrovskaya
Transfer of Heat with Bubble Boiling in a Large Volume - V. I. Subbotin,
D. N. Sorokin, and A. A. Tsyganok
REVIEWS
The Current State and Development Prospects of Nuclear Power Generation in
Industrially Developed Capitalist and Emergent Countries - V. D. Andreev
ABSTRACTS
Temperature Fields of Fuel Elements in the BOR Reactor Core - V. I. Subbotin,
P. A. Ushakov, A. V. Zhukov, and E. Ya. Sviridenko
Investigation of Temperature Fields in Fast Reactor Fuel Elements with Variable
Power Distribution over Height of Core - V. F. Dobrovol'skii, A. V. Zhukov,
E. Ya. Sviridenko, V. I. Subbotin, and P. A. Ushakov
Activation of Corrosion Products in the Primary Loop of a Pressurized-Water Reactor
- A. I. Kasperovich and N. V. Bychkov
Optimization of Parameters of Two-Group Approximation of Kinetics Equations by the
Method of Logarithmic Frequency Response - K. N. Prikot and
V. K. Uspenskii
Measurement of Certain Characteristics of Neutron Fluxes in Experimental Arrangements
of the SM-2 Reactor by Reference to Gold Activation - A. V. Klinov,
Yu. P. Kormushkin, V. V. Frunze, and V. A. Tsykanov
y-Radiation of Fission Products for a Short Period of Service on the Fuel in a Nuclear
Reactor - E. S. Stariznyi and A. Kh. Breger
Calculation of Efficiency of y-Irradiators - V. E. Drozdov and L. M. Dunaev
575
450
577
451
579
451
581
452
583
453
585
455
586
455
587
456
589
456
590
457
591
457
591
458
591
458
593
463
598
467
603
471
608
477
620
489
621
490
622
490
623
491
623
491
624
492
625
492
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One-Group Method of Calculating Dose Fields from Sources of 'y-Radiation with a Complex
Spectrum ? L. M. Dunaev, V. E. Drozdov, and N. I. Orlenko
Generalization of 'y-Albedo Calculations on the- Basis of Similarity Theory
? A. P. Ochkur, G. A. Pshenichnyi, and 0. S. Marenkov
Physicochemical Properties of Mixture's of Heavy Metal Fluorides. Communication III.
Phase Diagram of the Uraniuth Hexafluoride ? Niobium Pentafluoride System
? V. N. Prusakov and V. rc. Ezhov
?Physicochemical Properties of Mixtures of Heavy-Metal Fluorides. Communication IV.
Eng I./Russ.
626 493
627 494
629 496
Fusibility Diagram of the Xenon Difluoride ? Uranium Hexafluoride System
? V. K. Ezhov, V. N. Prusakov, and B. B. Chaivanov
630
497
Calculated Isomeric Cross Section Ratios in the Reaction Se80 (n, y) Se81m, g
? V. P. Koroleva
630
497
Contribution of the Theory of Transverse Instability in a Sectional Linear Accelerator
? V. I. Kurilko and A. P. Tolstoluzhskii
631
498
LETTERS TO THE EDITOR
Heat Transfer Criterion for Evaluating Quality of Axial Power Distribution in a Reactor
? Yu. P. Filin
633
500
Neutron Dose from an Isotropic Point Fission Source ? A. I. Khovanovich,
V. F. Kokovikhin, N. A. Kondurushkin, and V. Ya. Belovintsev
635
501
C11, NI--R , and F18 Yields during the Irradiation of Nitrogen by Protons, Deuterons, He3
Ions, and a-Particles ? N. N. Krasnov, P. P. Dmitriev, Z. P. Dmitrieva,
I. 0. Konstantinov, and G. A. Molin
637
503
Recording of Fission Fragments by Glass as a Function of the Period between the
Irradiation of the Glass and Its Etching ? V. K. Gorshkov
639
504
Radiation Detectors Using Semi-Insulating Cadmium Telluride ? V. S. Vavilov,
R. Kh. Vagapov, V. A. Chapnin, and M. V. Chukichev
641
505
Measurement of Nucleon Fluxes with Energies Greater than 600 MeV
? V. E. Borodin, A. V. Zotov, L. R. Kimel', V. N. Lebedev, and
V. P. Sidorin
643
506
On a Possible Mechanism for Increasing the Emittance of a Beam ? V. A. Teplyakov
645
508
The Shaping System and Parameters of the Beam of 'y-Quanta in an Electron
Accelerator Having an Energy of 2 GeV ? B. I. Shramenko, S. G. Tonopetian,
I. A. Grishaev, N. V. Goncharov, N. I. Lapin, V. I. Nikiforov, G. D, Pugachev,
and V. M. Khvorostian
648
509
Current Limiting in Linear Accelerators Due to the Longitudinal Space-Charge Forces
? G. I. Zhileiko and L. M. Movsisyan
651
511
The Instability of an Electron Beam in a Spatially Periodic Electric Field
? G. G. Aseev, G. G. Kuznetsova, N. S. Repalov, B. G. Safronov, and
N. A. KhizYmyak
654
513
NEWS
Conference on Nuclear Power Station Process Control and Monitoring Instrumentation
? V. V. Postnikov
657
515
Symposium on Operating Characteristics of Power Reactor Components
? B. A. Maslenok
660
516
All-Union Conference on the Thermodynamics of Metallic Alloys ? G. M. Lukashenko .
663
518
IV International Congress on Powder Metallurgy ? A. F. Islankina
664
518
Symposium on New Techniques in Making Radioactive Preparations ? V. I. Levin
667
520
Soviet Specialists Visiting the USA ? V. V. Stekol'nikov
669
521
Applications of Electron Irradiation in Potato Growing ? N. S. Batsanov
671
522
BOOK RE VIEWS
Collections of Standards for a Unified System of Design Engineering Documentation. . . .
673
524
1282
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L. S. Ruzer ? Radioactive Aerosols (Measurement of Concentrations and Absorbed
Engl./Russ.
Doses]
674
524
R. L. Long and P. D. O'Brien (editors) ? Fast Burst Reactors (Proceedings of the
National Topical Meeting, Jan. 28-30, 1969, Albuquerque, New Mexico)
675
525
G. L. Shaw and D. Y. Wong (editors) ? Pion-Nucleon Scattering
676
525
Volume 29, Number 1 July, 1970
Igor' Evgen'evich Tamm (On His 75th Birthday)
677
Some Features of Uranium Reserve Estimation in Sedimentary Rocks for
Underground Leaching ? V. P. Novik-Kachan
679
3
Determination of Core Temperatures in Liquid-Metal-Cooled Reactors
? N. I. Buleev, V. B. Levchenko, K. N. Polosukhina, and A. A. Sholokhov . .
683
6
The Method of Subgroups for Considering the Resonance Structure of the Cross
Sections in Neutron Calculations (Part 1) ? N. M. Nikolaev, A. A. Ignatov,
N. V. Isaev, and V. F. Kokhlov
689
11
Turbulent Flow in Pipes of Noncircular Cross Section ? M. D. Millionshchikov
696
16
Monitoring the Outside Environment of a Nuclear Power Station with a Boiling Water
Type Reactor ? V. A. Knyazev, P. I. Kotikov, V. G. Laptev, and
Yu. V. Chechetkin
699
18
Influence of the pH on the Sorption of Radioactive Isotopes by Anion-Exchange Resins
? F. V. Rauzen and T. S. Vedishcheva
703
21
Change of Properties of Leather Hides when Irradiated with Doses of 1-10 Mrad
? I. P. Strakhov, P. I. Lebenko, I. G. Shifrin, A. I. Metelkin,
V. P. A verkiev, Yu. F. Pavlov, and G. D. Rybakova
708
26
Channel for Negative Particles with Momenta to 60 GeV/c ? I. A. Aleksandrov,
M. I. Grachev, K. I. Gubrienko, E. V. Eremenko, V. I. Kotov,
A. N. Nekrasov, A. A. Prilepin, V. A. Pichugin, R. A. Rzaev,
A. V. Samoilov, V. S. Seleznev, B. A. Serebryakov, A. E. Khanamiryan, and
Yu. S. Khodyrev
712
29
A BSTRACTS
Application of the Method of Reduced Costs to Estimates? of the Effectiveness of
Utilization of Nuclear Fuel ? A. V. Taliev and A. Ya. Kramerov
718
36
Measurement of Effective Neutron Temperature in Uranium?Graphite Reactors
? S. S. Lomakin, T. S. Mordovskaya, G. G. Panfilov, V. I. Petrov,
P. S. Samoilov, and V. V. Khmyzov
719
36
An Express Method for Reconstructing the Spectra of Fast Neutrons in Nuclear-Physics
Installations during Measurement by Threshold Detectors ? V. S. Troshin and
E. A. Kramer-Ageev
719
37
The Spectrum of Scattered y-Radiation at Small Distances from the Source
? V. I. Utkin
721
38
On the Efficiency of Radiators and Absorbers of Charged Particles
? V. M. Lenchenko, E. V. Sazonova, and L. A. Sofienko
721
38
Electrical Engineering Properties of Porcelain Exposed to y -Radiation
? N. S. Kostyukov, V. V. Talyzin, M. I. Muminov, and M. I. Zil'berman . . . .
722
39
On the Trajectories of Particles in an Isochronous Cyclotron in the Presence of
Acceleration ? Yu. K. Khokhlov
723
39
LETTERS TO THE EDITOR
Mechanism Underlying the Emanation of Radioactive Ores and Minerals
? V. L. Shashkin and M. I. Prutkina
724
41
1283
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Radiation Circuit of the IRT Reactor of Tomsk Polytechnic Institute
? E. S. Sakharov, I. P. Chuchalin, A. G. Skorikov, R. I. Akimova, and
V. V. Karnaukhov
Generalized Relationship for Calculating Heat Transfer in the Developed Boiling of Alkali
Metals ? V. I. Subbotin, D. N. Sorokin, and A. P. Kudryavtsev
Density of Vapor-Formation Centers during Boiling at a Surface ? V. F. Prisnyakov .
Empirical Transmission Coefficients of Heavy Nuclei for 0.05- to 2-MeV Neutrons
? P. E. Vorotnikov
Engl./Russ.
727 43
730 45
732 46
735 48
Optimal Conditions for Neutron Activation Analysis for Continuous Determination of
Fluorite in a Current of Slurry ? V. I. Prokopchik
737
50
Thermalization Time of Fast Neutrons in Rocks of Silicate Composition and Different
Moisture Content ? B. M. Kolesov, G. I. Ganichev, A. K. Ovchianikov,
I. M. Khaikovich, and T. V. Timofeeva
739
51
The Electrification of Bodies by y-Radiation ? V. M. Lenchenko
742
53
NEWS OF SCIENCE AND TECHNOLOGY
XXVII Session of the Learned Council of the Joint Institute for Nuclear Research [Dubna]
? V. A. Biryukov
745
56
Twentieth All-Union Conference on Nuclear Spectroscopy and Nuclear Structure
? 0. E. Kraft and M. A. Listengarten
750
58
Soviet Delegation Visits Italy ? F. M. Mitenkov
753
61
Soviet Solid State Physics Specialists Touring Canada ? I. P. Sadikov
755
62
The K-200000 General-Purpose Radiation-Chemical Research Facility ? V. A. Gol'din
759
64
BRIEF COMMUNICATIONS
760
64
Volume 29, Number 2 August, 1970
Calculation of the Channel Rating of a Chemonuclear Reactor under Nonisothermal
Flow Conditions of the Gas Undergoing Radiolysis and Variable Dose
.Intensity
? B. G. Dzantiev, V. T. Kazazyan, A. K. Krasin, and G. V. Nichipor
763
71
Problems of Constructing Atomic Steam and Gas Plants ? E. F. Ratnikov
769
77
Resistivity of a-Plutonium Irradiated by Neutrons in Liquid Nitrogen
? S. T. Konobeevskii, V. M. Raetskii, and N. S. Kosulin
773
80
Transfer of Zinc Corrosion Products from Boiling Water to Steam and Distribution
of the Active Component throughout the Circuit of the VK-50 Boiling Water
Reactor ? 0. I. Martynova, A. I. Nazarov, Yu. V. Chechetkin,
I. G. Kobzar', Yu. F. Samoilov, and T. I. Petrova
776
82
Effect of Oxygen on Steel Corrosion in Steam ?Water Flows at a Temperature of 280?C
? K. A. Nesmeyanova
781
86
Energy Dependence of Neutron Transport Scattering Length in H2O, D20, and Graphite
? B. N. Goshchitskii, V. V. Gusev, L. V. Konstantinov, P. M. Korotovskikh,
S. K. Sidorov, V. V. Chernobrovkin, and V. G. Chudinov
786
91
Measurement of Energy Spectrum and Average Number of Prompt Fission Neutrons
? N. I. Kroshkin and Yu. S. Zamyatnin
790
95
Salting Out in the Extraction of Acids and Certain Radioactive Elements.
Communication IV. Salting Out in the Extraction of HNO3, UO2 (NO3)2, and
Th(NO3)4 by Amines and Tri-n-Butyl Phosphate ? Yu. G. Frolov,
? G. I. Nasonova, and N. V. Gavrilov
794
99
Study of the Sorption of Strontium and Calcium Cations on the Cation-Exchange Resin
KU-2 ? F. V. Rauzen and N. P. Trushkov
798
103
Equilibrium and Stability of Plasma in Closed Traps without Rotational Transformation
? V. D. Shafranov and E. I. Yurchenko
801
106
1284
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System for Monochromatization of the External Beam of a 2.4-Meter Isochronous
Cyclotron ? Yu. G. Basargin, V. I. Bogdanova, N. I. Venikov, K. N. Korol',
Engl./Russ.
N. N. Posel'skii, and Yu. P. Severgin
809
112
?A BSTRA C TS
Some Problems of Kinetics of Coupled Rectors ? V. V. Vatulin and V. I. Yuferev. . .
815
117
Angular Distribution of Neurons Scattered in Air from a Monoenergetic Isotropic Point
Source ?V. F. Kokovikhin, N. A. Kondurushkin, V. Ya. Belovintsev, and
V. V. Barchugov
816
118
Angular and Energy Distributions of y-Rays in Lead ? B. S. Kondrat'ev
817
119
System for Recording the B12 Isotope Which Is Formed According to the C12(n, p)
Reaction ? V. T. Tustanovskii, V. I. Andriushchenko, and A. A. Vol igemut .
818
119
Activation-Analysis Determination of the Silver Content in Microcrystal Centers in a
Photographic Emulsion ? L. E. Potap'eva and V. I. Kalashnikova
819
120
Accelerating System with Parallel Connected Gaps ? B. K. Shembel', I. I. Sulygin,
E. S. Nelipovich, and V. V. Osipov
820
121
A Possible Method of Accelerating Heavy Ions ? N. I. Tarantin
821
122
Depolarization of Protons in a Phasotron with Spatial Variation of the Magnetic Field
? Yu. A. Plis and L. M. Soroko
822
122
On Increasing the Efficiency of Alternating-Phase Focusing in Linear Accelerators
? V. V. Kushin
823
123
Spatial Generalization of Nomographs with an Oriented Transparency Grid, and Their
Use in the Kinematics of Nuclear Reactions ? G. N. Potetyunko
824
124
LETTERS TO THE EDITOR
Optimum Dimensions of the Working Volumes of Various Units in Radiation Circuits
? E. S. Sakharov and I. P. Chuchalin
826
125
Track-Delimiting Autoradiography for Studying Microdistributions of Some Elements in
Metals ?M. A. Krishtal, L. I. Ivanov, and E. M. Grinberg
829
127
Value Function in Cascades for the Separation of a Multicomponent Isotope Mixture
? I. A. Kolokol 'tsov, V. I. Nikolaev, G. A. Sulaberidze, and S. A. Tret'yak
832
128
An Analysis of V as a Function of Neutron Energy Based on the Energy Balance in Nuclear
Fission ? V. G. Vorobteva, P. P. D'yachenko, B. D. Kuz'minov,
A. I. Sergachev, and L. D. Smirenkina
835
130
One Possible Method of Identifying the Products of Nuclear Reactions Taking Place under the
Influence of Heavy Ions ? V. A. Druin, Yu. V. Lobanov, and Yu. P. Kharitonov .
837
132
Method of Separation of Dose Strength of y-Radiation of Artificial and Natural
Radioactive Isotopes in Soils ? V. A. Vorob'ev, R. M. Kogan. I. M. Nazarov,
and Sh. D. Fridman
840
133
Altitude Distributions of U238, Th232, and Pu239 in Atmospheric Fallout
? B. I. Styro, N. K. Shpirkauskaite, and V. M. Kuptsov
843
135
Experimental Study of the Scattering of an Ion Beam in a Plasma with Hot Electrons
? G. S. Kirichenko and V. G. Khmaruk
845
136
Beam Shaping System and Beam Parameters in Extraction Channels of 360 MeV
Linear Electron Accelerator ? I. A. Grishaev, G. K. Dem'yanenko,
L. A. Makhnenko, K. S. Rubtsov, and P. M. Ryabka
847
138
The U-13 10 MeV Linear Electron Accelerator ? 0. A. Val'dner, 0. S. Milovanov,
V. A. Ostanin, E. G. Pyatnov, N. P. Sobenin, I. A. Smirnov, and
I. S. Shchedrin
850
140
Proton Current Attainable in Large Equilibrium Phases in a Linear Accelerator with No
Particle Losses ? A. D. Vlasov
852
141
1285
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Volume 29, Number 3 September, 1970
Engl./Russ.
Electronuclear Generation of Neutrons (Editorial Comment)
857
151
The Electronuclear Method of Generating Neutrons and Producing Fissionable
Materials ? V. G. Vasil'kov, V.I. Gol'danskii, V. P. Dzhelepov, and
V. P. Dmitrievskii
858
151
On Electronuclear Breeding ? V.A. Davidenko
866
158
High-Flux Continuous Research Reactors and Their Prospects ? S. M. Feinberg. . . .
870
162
Ampoules for Material Irradiation in the SM-2 High-Flux Reactor ? V.A. Tsykanov,
B. V. Samsonov, R. A. Timchenko, .V. N. Shulimov, and G. P. Lobanov
876
169
Behavior of Beryllium Metal in the SM-2 Reactor ? Z. I. Chechetkina, V. P. Gol'tsev,
V.I. Klimenkov, S. N. Votinov, and V.A. Tsykanov
882
174
Uranium Strengthened with Beryllium Oxide Particles ? A. I. Voloshchuk,
G. S. Gaidamachenko, Yu. M. Golovchenko, V. F. Zelenskii, V. E. Ivanov, and
Yu. F. Konotop
886
178
Pile Testing of VNPM-1 Organosilicate Molding Compound in Core of IVV-2 Reactor
? N. P. Kharitonov, V.A. Krotikov, and B. V. Lysikov
893
184
REVIEWS
Intermediate Structure in Neutron Cross Sections ? S. I. Sukhoruchkin
896
187
Microdosimetry (Physical Aspects and Basic Problems) ? V.I. Ivanov
904
195
A BSTRA C TS
Temperature Dependence of Diffusion Parameters of Slow Neutrons in Zirconium
Hydride ? A. V. Antonov, B. V. Granatkin, M. V. Kazarnovskii,
Yu. A. Merkul' ev, V. Z. Nozik, and M. S. Yudkevich
910
201
Use of the Method of Lagrange Multipliers for Optimization of Nuclear Reactors
?E.G. Sakhnovskii
911
201
Determination of Vapor Content by Means of Flow Meters ? V. V. Vazinger
911
202
Determination of the Spectral and Angular Distribution of y-Quanta in Flat Barriers
Containing Radiation Sources ? S.A. Churin
913
203
Analysis of the Photopeak of Scintillation y-Spectra ? Ch. Stoyanov, L. Aleksandrov,
and V. Gadzhokov
914
203
Stopping Electrons with Matter ? V.A. Kononov, K. A. Dergobuzov, and V. M. Zykov
914
204
Note on Optimized Conditions in X-Ray Absorptiometry ? A. E. Ignatenko
and A. D. Kulykov
915
204
The Yields of V48 in Nuclear Reactions on a Cyclotron ? P. P. Dmitriev,
1.0. Konstantinov, and N. N. Krasnov
916
205
Methods of Obtaining Cr81 on a Cyclotron ? C. P. Dmitriev, 1.0. Konstantinov, and,
N. N. Krasnov-917
206
Measurement of the Energy Spectra of Electrons in the LUE-25 Linear Accelerator
? V.1. Ermakov, V. P. Kovalev, I. A. Prthinikov, M. S. Susloparov, A. S. Toropov,
S. P. Filipenok, and V. P. Kharin
918
206
LETTERS TO THE EDITOR
Reliability of the Evaporation Channels of Reactors of the Beloyarsk Atomic Power Station
Type ? L. V. Konstantinov, V. V. Postnikov, V. N. Vetyukov, and L. I. Lunina . .
920
208
The Effect of Versene Treatment on the Hydrogenation of Steel ? T. Kh. Margulova,
V. V. Gerasimov, and A. A. Lipanina
923
209
Continuous Diffusion Type Gage Indicating the Hydrogen Present in Sodium
? V.I. Subbotin, F. A. Kozlov, E.K . Kuznetsov, N. N. Ivanovskii, and
V. V. Matyukhin
925
210
Measurements of Reactivity by Pulse Methods ? E. A. Stumbur
928
212
Determination of the Reactivity Margin by the Method of Double Overcompensation
? T. S. Dideikin and B. P. Shishin
932
215
1286
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The Doppler Effect and Nuclear Safety of a Fast-Neutron Reactor - G. B. Usynin and
Engl./Russ.
L. N. Polyanin?
935
216
Ratios of Fast Fission Cross Sections of U235, PU239, and Pu240 - M.V. Sabin,
Yu. A. Khokhlov, Yu. S. Zamyatnin, and I. N. Paramonova
938
218
Diffusion of Nickel in Beryllium - V. M. Anan'in, V. P. Gladkov, V. S. Zotov,
D. M. Skorov
941
220
NEWS
Scientific Conference of Moscow Engineering and Physics Institute [MIFI] - V. V. Frolov
944
222
II All-Union Symposium on the Chemistry of Inorganic Fluorides - Yu. A. Buslaev
948
224
V Session of the International Communications Group on Thermionic Generation of
Electric Power - Yu. I. Danilov and D. V. Karetnikov
951
225
Isotopes in Hydrology - Yu. A. Izraell
954
227
Soviet Specialists Visit Denmark - L. Zolinova and V. Khrushchev
956
228
A New Show at the "Atomic Energy" Pavilion of the Expositiori of Achievements of the
National Economy of the USSR - V. M. Kaloshin
958
229
BRIEF COMMUNICATIONS
964
234
Volume 29, Number 4 October, 1970
The Synthesis of Element 105 - G. N. Flerov, Yu. Ts. Oganesyan, Yu. V. Lobanov,
Yu. A. Lazarev, S. P. Tret'yakova, I. V. Kolesov, and V. M. Plotko
967
243
Use of Uranium Hexafluoride in Nuclear Power Plants - V. A. Dmitrievskii,
E. M. Voinov, and S. D. Tetel'baum
976
251
Potential Danger of Embrittlement in Structures Made of Type 22K Steel
- A. S. Dovzhenko
981
255
Optimum Irradiation Procedure for the Production of Isotopes - V. P. Terent'ev,
V. A. Zharkov, G. M. Fradkin, and T. P. Chavychalova
986
260
Production of Isotopes in Fission Reactions - Yu. Ts. Oganesyan,
Yu. E. Penionzhkevich, A. 0. Shamsutdinov, N. S. Mal tseva, I. I. Chuburkova,
and Z. Sheglovskii
990
264
Transverse Beam Characteristics at the Entrance of the IHEP Proton Synchrotron
- D. A. ?Demikhovskii, E. A. Myae, and E. F. Troyanov
998
272
Study of the Conditions of Forming a Dense Plasma on Injecting an Electron Beam into
a Magnetic Trap - M. Yu. Bredikhin, A. M. Iltchenko, A. I. Maslov,
'A. I. Skibenko, E. I. Skibenko, and V. B. Yuferov
1003
276
ABSTRACTS
Microdistribution of Fission Density in VVR-M (Water-Cooled Water-Moderated
Reactor) Critical-Assembly Loop Converter Cells - V. B. Klimentov,
G. A. Kopchinskii, and V. G. Bobkov
1009
283
Some Integral-Reactivity Properties and Their Application to the IGR Reactor
- V. D. Lavrenikov
1010
283
Note on the Determination of Neutron Diffusion Constants - L. Aleksandrov,
A. Stanolov, and V. Khristov
1010
283
Precipitation of Uranium from a Melt of Fused Halides with a Molten Zinc Cathode
- A. V. Volkovich, I. F. Nichkov, S. P. Raspopin, and Yu. P. Kanashin
1011
284
Contribution to the Determination of the Energy Loss of Relativistic Electrons in Thick
Lead and Tungsten Targets - V. D. Anan'ev and I. M. Matora
1012
285
Distribution of Gamma Radiation at a Shield Boundary from Sources Having Arbitrary
Angular Distributions - A. Viktorov, B. A. Efimenko, V. G. Zolotukhin,
V. A. Klimanov, and V. V. Mashkovich
1013
286
1287
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y-Ray Induced Scintillation ? A. V. Zhemerev and Yu. A. Medvedev
Secondary Contamination of the Surface of a Material by Absorbed Radioactive
Substances ? A. L. Kononovich and E. M. Perfilova
LETTERS TO THE EDITOR
Loop for Studying the Electrical Conductivity of Irradiated Materials in a VVR (Water-
Co',1ed Water-Moderated) Reactor ? A. G. Kharlamov, N. P. Zakharova,
A. A. Batalov, Yu. I. Zaikin, and V. I. Kolyadin
Study of the Development of Leakages in Fuel Element Cans by Means of Kr88
? G. A. Kotel'nikov and V. F. Leonov
Effect of Fuel Element Dimensions on Heat Emission under Supercritical Pressure
? N. L. Kafengauz and M. I. Fedorov
The Radiation Resistance of Beryllium Oxide at Various Temperatures
? V. I. Klimenkov and A. V. Khudyakov
Rhenium and Its Alloys with Boron?Effective Neutron Absorbers ? B. G. Arabei,
V. I. Matveev, V. P. Smirnov, and K. I. Frolova
Inertialess Monitoring of the Reactor Power Level with Respect to the y-Radiation
Intensity ? I. Ya. Emel'yanov, L. V. Konstantinov, V. V. Postnikov,
V. I. Potapkin, and Yu. M. Serebrennikov
Theory of Asymmetrical Separating Cascades with Arbitrary Degrees of Enrichment in
the Separating Unit ? N. A. Kolokol'tsov and N. I. Lagunstov
Deposition of Uranium in the Bones of Animals ? 0. Otgonsuren, V. P. Perelygin,
and D. ChuItem
Mechanism Underlying the Formation of Dendritic or Tree-Like Channels in a
Dielectric Irradiated with Charged Particles ? Yu. S. Deev, M. S. Kruglyi,
V. K. Lyapidevskii, and V. I. Serenkov
Determination of Radiothorium Content by Means of Delayed Coincidences of
Disintegrations of Tn220 and Po218 ? A. A. Pomanskii and S. A. Severnyi
NEWS
Second Congress of the International Association of Radiation Protection
? 0. A. Kochetkov, E. A. Kramer-Ageev, and V. N. Lebedev
International Conference on the Diagnostics of a Hot Plasma ? M. I. Pergament
International Conference on Microelectronics ? A. N. Sinaev
Fifteenth Yugoslavian Symposium "YuREMA-70" ? V. F. Sikolenko
Regular Session of TC-45 of the IEC ? V. V. Matveev and V. S. Zhernov
Uranium Industry in the Developing Countries and in the Industrially Developed
Capitalist Countries in 1969 ? V. D. Andreev
BRIEF COMMUNICATIONS
Volume 29, Number 5 November, 1970
Application of y-Chambers for the Power Measurements of Fuel Channels of the
Beloyarsk Atomic Electric Power Plant ? I. Ya. Emel'yanov, V. I. Alekseev,
L. V. Konstantinov, V. V. Postnikov, Yu. M. Serebrennikov, E. I. Snitko,
G. A. Shasharin
Optimization of the Structure of a Developing System of Atomic Power Stations Allowing
for Changes in the Load Factor ? W. Frankowski
Cross Sections for the Production of y-Rays as a Result of Inelastic Scattering of
Neutrons of a Fission Spectrum ? A. T. Bakov, V. G. Dvukhsherstnov,
and Yu. A. Kazanskii
Electrolytic Isolation of Plutonium from Solutions of Formic Acid ? A. G. Smartseva
and Z. A. Zhuravleva
1288
Engl./Russ.
1014
287
1015
287
1016
289
1019
291
1022
293
1024
294
1026
295
1029
298
1032
300
1035
301
1037
303
1041
305
1044
307
1046
308
1048
309
1051
310
1052
311
1054
312
1065
320
1067
327
1071
330
1080
338
1085
342
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A High-Current Accelerator that Produces 1.2 MeV Protons ? E. A. Abramyan,
M. M. Brovin, V. V. Vecheslavov, V. A. Gorbunov, V.1. Kononov, and
Engl./Russ.
I. L. Chertok
1089
346
Effect of Space Charge on the Stability of Betatron Oscillations in Circular Accelerators
? A. A. Kolomenskii and A. T. Polukhin
1095
352
Investigation of the Effect of Secondary Charged Particles on a Proton Beam in a
Betatron Mode ? G. I. Dimov, V. G. Dudnikov, and V. G. Shamovskii
1100
356
ABSTRACTS
A Method for Determining the Coefficients of Reactor Transfer Functions
? S. A. Pridatko and A. S. Trofimov
1107
362
The Possibility of Variations in Unit Pulses of Radiative Heat ? S. S. Ogorodnik and
Yu. L. Tsoglin
1108
362
Protection against Reactor Emergencies Associated with Reactivity Perturbations
? G. G. Grebenyuk, M. Kb. Dorri, and M. M. Soloviev
1109
363
Corrosion and Electrochemical Behavior of a Zirconium Alloy with 2.5% Niobium in
Water and Steam at High Temperature ? A. I. Gromova, V. V. Gerasimov,
N. A. Kabankova, I. G. Shut'ko, and E. V. Volkhonskii
1110
364
Resonance Neutron Moderation in Matter (Part Three) ? D. A. Kozhevnikov and
V. S. Havkin
1111
365
Investigation of Buildup Region for y-Radiation from Low-Level Sources
? R. V. Stavitskii, P. A. Yarkavoi, and M. V. Kheteev
1112
366
Using a Photoelectric Colorimeter for Counting Charged Particle Tracks on the Surface
of Glass Detectors ? A. I. Khovanovich, G. L. Pikalov, and I. F. Kryvokrysenko
1113
367
Determination of the Wear of Machine Parts by Charged-Particle Activation
?1. 0. Konstantinov and N. N. Krasnov
1114
367
Activation of the Concrete Shield of the Offal Synchrocyclotron by Scattered Radiation
? L. N. Zaitsev, L. R. Kimel' , and V. P. Sidorin
1115
368
LETTERS TO THE EDITOR
Effective Calculation of One-Dimensional Nuclear Reactors without Using Networks
? E. S. Glushkov, N. N. Ponomarev-Stepnoi, and N. A. Petushkova
1116
370
Theory of the Method of a Pulsed Neutron Source in Heterogeneous Media
? A. V. Step anov
1119
371
Reactivity-Measurement Determination of the Relative Number of Fissions by
Epithermal Neutrons ? V. E. Demin and 0.N. Smirnov
1121
372
Critical Heat Fluxes during Boiling of High-Boiling Heat Carriers ? L. S. Sterman
and J. Korychanek
1124
374
Automated System for Indicating Presence of Impurities in Sodium Coolant Stream
? A. N. Mitropol'skii, M. S. Pinkhasik, A. A. Petrenko, I. Kh. Tsukerman,
and V. D. Tarantin
1126
376
Weakening of the Flux of High-Energy Neutrons in a Cylindrical Channel
? N. I. Bushuev, A. N. Kargin, V. V. MaPkov, and B. S. Sychev
1129
378
How Irradiation Affects the Electrical Resistance of Alloys of Uranium with Zirconium
and Niobium ? V. M. Raetskii, A. Ya. Zavgorodnii, and LI. Gomozov
1131
379
On the Theory of the Effect of Neutron Bombardment of Metal Creep ? L. N. Ovander
1133
381
On the Possible Endogenous Origin of Certain "Secondary" Uranium Minerals
? G. N. Kotel 'nikov
1135
382
Selection of Zones Suitable for Burial of Industrial Waste ? V. G. Tyminskii and
A. I. Spiridonov
1137
383
Estimated Diffusion of Materials through Clayey Soil ? P. F. Dolgikh, L.A. Vladimirov,
and F. P. Yudin
1140
385
Instability Boundary of Trapped Particles in a Finite-Pressure Plasma in Toroidal
Systems ? V. N. Kursakov
1144
388
1289
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Experimental Study of the Linear Polarization of Electron Synchrotron Radiation at High
Energies ? A. A. Vorob'ev, M. M. Nikitin, and A. V. Kozhevnikov
A Nomogram for Determining the Range of Protons ? V. V. Nestrelyaev and
G. N. Potetyunko
Eng1./Russ.
1146 389
1149 391
NEWS
VI All-Union Nuclear Physics School ? L. N. Sukhotin and K. A. Korotkov
1150
392
The Gordon Conference (Seattle, June 1970) on Plasma Physics ? V. P. Sarantsev
1152
393
Franco-Soviet Seminar on Nuclear Data for Reactor Design Calculations
? L. N. Usachev
1156
395
I Scientific Practical Workshop Conference on Applications of Isotopes and Ionizing
Radiations in Agriculture ? D. A. Kaushanskii and B. G. Zhukov
1159
397
The RKhM-y-20 Multichamber y-Irradiator for Radiation Research ? D. A. Kaushanskii
1162
398
Operating Experience with the "Beta-S" Radioisotope Thermoelectric Generators
? N. P. Korotkov, A. I. Ragozinskii, and G. M. Fradkin
1165
400
Has Element 108 Been Discovered? ? V. M. Kulakov
1166
401
BRIEF COMMUNICATIONS
1169
402
BOOK REVIEWS
A. S. Solovkin and G. A. Yagodin ? Extractive Chemistry of Zirconium and Hafnium.
Part 1 ? Reviewed by V. V. Sergievskii
1173
405
F. I. Pavlotskaya, E. B. Tyuryukanova, and V. I. Baranov ? Global Propagation of
Radioactive Strontium over the Earth's Surface ? Reviewed by R. M. Aleksakhin
1174
405
Atomwirtschaft 1970 Yearbook.
1174
405
H. Weckesser ? Operation of Nuclear Power Plants
1175
406
Biological Implications of the Nuclear Age
1176
406
Radiation Biology of the Fetal and Juvenile Mammal
1176
406
Volume 29, Number 6 December, 1970
On the Sixtieth Birthday of Boris Sergeevich Dzhelepov, Corresponding Member of the
Academy of Sciences of the USSR
1177
Turbulent Heat and Mass Exchange ? M. D. Millionshchikov
1178
411
Special Aspects of the Deformation of Uranium Subjected to Tensile Stain at a Constant
Velocity ? A. I. Voloshchuk, V. F. Zelenskii, Yu. F. Konotop,
and Yu. T. Miroshnichenko
1184
416
Subbarrier Neutron Fission of PU238 (Err) - S. B. Ermagambetov and G. N. Smirenkin
1190
422
Design of Cascades for Separating Isotope Mixtures ? N. A. Kolokolitsov,
V. P. Minenko, B. I. Nikolaev, G. A. Sulaberidze, and S. A. Tret'yak
1193
425
Storage of Multiply-Charged Ions in a Relativistic Electron Bunch
? M. L. Iovnovich and M. M. Fiks
1199
429
Energy Balance in the Plasma in Apparatuses of the "Tokamak" Type
?Yu. N. Dnestrovskii and D. P. Kostomarov
1205
434
RE VIEWS
Thermodynamics of the Uranium?Carbon, Uranium?Nitrogen, and Plutonium?Carbon
Systems ? V. V. Akhachinskii and S. N. Bashlykov
1211
439
ABSTRACTS
Slowing Down of Resonance Neutrons in Matter. Communication 4 ? D. A. Kozhevnikov
and V. S. Khavkin
1220
448
1290
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Declassified and Approved For Release 2013/04/09: CIA-RDP10-02196R000700060001-1
Investigation of the Calibration Characteristics of a Radiation Thermodiverter in
High-Intensity Fields of Ionizing Radiations - V. S. Karasev, S. S. Ogorodnik,
Engl./Russ.
and Yu. L. Tsoglin
1221
449
Calculation of Photoneutron Distribution by Monte Carlo Method - A. A.Morozov
and A. I. Khisamutdinov
1222
449
Precision System for the Determination of Oxygen by Fast Neutron Activation
- I. P. Lisovskii and L. A. Smakhtin
1223
450
VVR Reactor Semiautomatic Activation Analysis System - I. P. Lisovskii,
L. A. Smakhtin, N. V. Filippova, and V. I. Volgin
1223
450
Method of Attenuating Radial Betatron Oscillations in Cyclic Accelerators
- L. A. Roginskii and G. F. Senatorov
1224
450
Permanent Electromagnet with Built-in Radioisotope Thermoelectric Direct Converter
- A. Kh. Cherkasskii and V. S. Makarov
1225
451
LETTERS TO THE EDITOR
Experimental Study of the Characteristics of the IR-100 Research Reactor
- L. V. Konstantinov, I. N. Martem'yanov, V. A. Nikolaev, A. A. Sarkisov,
V. F. Sachkov, A. V. Sobolev, S. V. Chernyaev, and I. S. Chesnokov
1227
453
Effect of the Flow Velocity of a Vapor-liquid Mixture of Coolant, and of Vapor
Content, on Surface Heat-Transfer Coefficient in Boiling of Water Inside Tubes
-F. F. Bogdanov
1229
454
Neutron Yield from Thick Targets Bombarded with 11.5 and 23.5 MeV Protons
- V. K. Daruga and E. S. Matusevich
1233
456
A Method of Determining the Iron Content of Corrosion Product Deposits
-B. A. Alekseev, N. N. Kozhenkov, and G. A. Kotel'nikov
1235
458
Group Separation of Fission Products by the Chromatographic Method
- L. N. Moskvin and N. N. Kalinin
1236
458
Experimental Verification of the Radiation-Chemical Method for Producing
Tetrachloroalkanes - A. A. Beer, P. A. Zagorets, V. F. Inozemtsev,
L. S. Maiorov, V. I.Slavyanov, G. A. Artyushov, I. F. Sprygaev,
and V. A. Novozhilov
1240
461
Use of Xenon Proportional Counter Escape Peaks for X-Ray Radiometric Analysis
of Tungsten in Ores - N. G. Bolotova, V. V. Kotelinikov, and E. P. Leman
1243
463
Diagnostics of an Electron-Ion Bunch U sing Bremsstrahlung - M. L. Iovnovich,
V. P. Sarantsev, and M. M. Fiks
1245
465
Excitation of Radial Betatron Oscillations by a Longitudinal Accelerating Field
- Yu. S. Ivanov, A. A. Kuz' min, and G. F. Senatorov
1248
467
NEWS
Liege May 1970 International Symposium on Modern Electric Power Generating
Stations - P. A. Andreev
1251
470
June 1970 Princeton Symposium on Plasma Stabilization by Feedback and Dynamical
Techniques - D. A. Panov
1253
471
June 1970 Zakopane Symposium on Nondestructive Materials Testing Equipment and
Techniques Using Nuclear Radiations - A.Maiorov
1256
473
The Saturn-1 Plasma Machine - V. A.Suprunenko
1259
474
The Anglo-Soviet Plasma Physics Experiment - V. V.Sannikov
1260
475
GKIAt -JINR Agreement on Scientific and Technical Collaboration - V.Biryukov.
1262
475
BRIEF COMMUNICATIONS
1263
476
INDEX
Author Index, Volumes 28-29, 1970
1267
Tables of Contents, Volumes 28-29, 1970
1273
1291
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? ALGEBRA
AND LOGIC
A cover-to-c'Over translation i of Algebra 1 kigika
A publication of the Institute of Mathematics, Siberian
Section of the Academy of Sciences of the USSR
Novosibirsk, SSR
Editor-in-chief: M. I. Kargapolov
Institute 'of Mathematics, Siberian Branch
Academy of Sciences of the USSR
Members of the Editorial Board:
Yu. L. Ersh6v
Yu. I. Merzlyakov
A. I. Shirshov
Translated from Russian
A new Soviet journal which publishes, at
bimonthly intervals, results of the latest re-
search in the areas of modern general alge-
? bra and of logic considered primarily from
an algebraic viewpoint. The algebraic pa-
pers, constituting the major part of the con-
tents, are concerned with studies in such
fields as ordered, almost torsion-free, nilpo-
? tent, and metabelian .groups, isomorphism
rings, Lie algebras, Frattini subgroups, and
clusters of algebras. In the area of logic, the
periodical covers such topics as hierarchical
sets, logical automata, and recursive func-
tiohs.
As is the case with all Consultants Bureau
journals, Algebra and Logic appears in Eng-
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publication of the Russian edition. Transla-
tion began with the 1968 issues.
.Contents of the first issue (Number 1, 1968):
A. A. Akataev and D. M. Smirnov, Lattices of submani- -
folds of manifolds of algebras ? G. F. Bachurin, On al-
most torsion-free nilpotent groups ? L. A. Bokut', On
the extension of ring isomorphisms ? Yu. L. Ershov, On
one hierarchy of sets, I ? V. V. Koz'mlnykh, On one:
place primitively-recursive functions ? A. I. Kokorin
and G. T. Kozlov, Extended elementary and universal
theories of lattice-ordered Abelian groups with a finite
number of threads ? Yu. I. Merzlyakov, On groups al-
most approximatable by finite p-groups ? V. P:Shunkov,
On a periodic group w.th'altnost regular involutions.
Contents of the Second issue (Number 2,1968):
V. N. Agafonov, The complexity of computing pseudo-
random sequences ? V. M. Kopytov and I. I. Mamaev,
Absolute convexity of certain subgroups of an ordera-
ble group ? S. P. Kogalovskil, On compact classes of
algel?raic systems ? E. N. Kuz'min, Algebraic sets in
Mal'tsev algebras ? I. A. Lavrov, The answer to a ques-
tion by P. R. Young ? L. L. Maksimova, On the strict
implication calculus ? E. A. Polyakov, Certain aspects
of the theory of recursive functions ? V. G. Sokolov, On
the Frattini subgroup .? M. A. Taltslin, On elementary
theories of lattices of ideals in polynomial rings.
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?
A New Volume in the Highly Acclaimed Series
A MONOGRAPHS IN SEMICONDUCTOR PHYSICS*
Series translated from Russian by Albin Tybulewicz
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Volume 3: SWITCHING c IN SEMICONDUCTOR DIODES \
By Yurii R. Nosov
A. F. loffe PhysicoteChnical Institute'
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Covers the physical basis of the operation
of a semiconductor diode under pulse con-
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electric field in fy diode base on transient processes
Transient processes in diodes during the passage of a
forward current pulse ? Transient processes in semi
conductor diodes and fundamentals of recombination
theory ? Literature cited ? Index.
Approx. 239 pages , PP ' 1969 , $19.50 ,
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SEMICONDUCTING II-VI, -
IV-VI, AND V4Il COMPOUNDS,
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The first published review of semiconducting,
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234 p&ges PP 1969 $19.50
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By V. M. Glazov, S. N. Chizhevskaye,
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Baikov Institute of Metallurgy
'Academy of Sciences of the USSR. Moscow
The first to deal with 'semiconductor's in the
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