THE SOVIET JOURNAL OF ATOMIC ENERGY VOLUME 11, NO. 3

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• Publication Date: March 1, 1962
• Content Type: REPORT

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Volume 11, No. 3
THE SOVIET JOURNAL OF
March, 1962
03111IC ENERGY
ATOMI1a51
1-leprli.51
\
TRANSLATED F!2aM RUSSIAN
- CONSULTANTS BUREAU
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LIQUID-METAL HEAT TRANSFER MEDIA
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I. I. Pioiikov and 0. S. Fedynskii
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EDITORIAL BOARD OF
ATOMNAYA ENERGIYA
A. I. Alikhanov
A. A. Bozhvar
N. A. Dollezhal
D. V. Efremov
V. S. Emel'yanov
V. S. Fursov
V. F. Kalinin
A. K. Krasin
A. V. Lebedinekii
A. I. Leipunekii
I. I. Novikov
(Editor-in-CM/)
B. V. Semenov
V. I. Vekeler
A. P. Vinogradov
N. A. Vlaeov
(Assistant Editor)
A. P. Zetirov
THE SOVIET JOURNAL Of
ATOMIC ENERGY
A translation of ATOMNAYA ENERGIYA,
a publication of the Academy of Sciences of the USSR
(Russian original dated September, 1961).,
Vol. 11, No. 3 March, 1962
CONTENTS
Acceleration of Hes up to 35 Mev in the One and One-Half Meter Cyclotron.
N. I. Venikov, G. N. Golovanov, V. P. Konyaev, N. V. Starostin,
and N. I. Chumakov
Silicon Counters for Nuclear Spectrometry. S. M. Ryv kin , L. V. M as lov ,
0. A. Matveev, N. B. Strokan, and D. V. Tarkhin
Two-Dimensional Boundary Problem for Two-Dimensional Square Lattices. L. Trl if a
Diffusivity of Sodium and Lithium. I. I. Rudnev , V. S. Lyashenko. and
M. D. Abramovich
Vasilii Savvich Lyashenko
Preparation of Highly Pure Beryllium by the Chloride Method. I. E. Vii 'komirs kii ,
G. F. Silina, A. S. Berengard, and V. N. Semakin
The Separation Factor of Lithium Isotopes during Vacuum Distillation.
S. G. Katal'nikov and B. M. Andreev
? ? ?
f
LETTERS TO THE EDITOR
The Angular and Energy Dispersion of "-Mesons in the Scatterd Magnetic Field of a Six-Meter
Synchrocyclotron.V. G. Kirillov, -Ugryumov, A. A. Kropin,
V. S. Roganov, and A. V. Samoilov
Improving the Monochromaticity of an Ion Beam in a Cyclotron. N. I. V en ikov and
N. I. Chumakov
The Angular Anisotropy of Fission of Even-Even Nuclei. V. G. N es t e rov
G. N. Smirenkin, and I. I. Bondarenko
The Possibility of the Practical Use of Isomers. Yu. V. Petrov
The Space Distribution of Fast Fission Neutrons in Iron. V. P. Mash kov ich and
S. G. Tsypin
The Problem of Thermal Contact Resistance during Heat Transfer to Liquid Metals.
0. P. Astakhov, V. I. Petrov, and 0. S. Fedynskii
The Thermodynamics of the Reduction of Uranium Tetrafluoride by Calcium.
N. P. Galkin, U. D. Veryatin, and Yu. V. Smirnov
NEWS OF SCIENCE AND TECHNOLOGY
Tenth Session of the Learned Council of the Joint Institute for Nuclear Research.
V. Biryukov
International Conference on Theoretical Aspects of Phenomena Occurring at Very High
Energies. V. S. Barashenkov
RUSS.
PAGE PAGE
857 213
861 217
865 221
877 230
881 232
882 233
889 240
894 245
898 247
901 248
903 250
905 251
910 255
914 257
918 261
919 262
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CONTENTS (continued)
RUSS.
PAGE PAGE
Use of Tritium in Physical and Biological Research. Ya. M. Vars ha vskii and
A. A. Ogloblin
Seminar on the Use of Isotopes and Nuclear Radiations in Blast-Furnace Production.
P. L. Gruzin
[Trends in the Design of British Nuclear Power Stations
922
927
264
268
Source: Nucl. Engng. 6, 100 (1961) No. 58
269]
[The Role of the AGR in British Power Program
Source: Nucl. Engng. 6, No. 59, 151 (1961)
270]
[First News on Operation of the Yankee Power Station
Source: Nucleonics, March, 1961
271]
[Nuclear Power Costs
Source: Nucl. Engng., 6, No. 60, 216 (1961)
273]
[In-Pile Testing of Nuclear Direct Conversion Device
Source: R. Howard et al. ARS Space Power Systems Conf., Sept., 1960
275]
[Metals Compatability in Gas-Cooled Reactors
Source: Nucl. Engng., 6, No. 60, 217 (1961)
277]
[On the Use of Carbon Steel in the NPR Reactor
Source: Nucleonics, March, 1961
277]
[A New Radiometric Separator for Enriching Uranium Ores, and Its Application
Sources: Mine and Quarry Engng., 25, No. 1, 46(1959); Engng. and Mining J., 160,
No. 2, 158 (1959); S. Afric. Mining J., 72, No. 3551, 409 (1961)
279]
[A New Concept in Manipulators
Source: Nucl. Engng. 6, No. 59, 173 (1961)
282]
BIBLIOGRAPHY
New Literature
933
287
Engineering and Physics Journal Inzhenerno-Fizicheskii Zhumal
943
294
NOTE
The Table of Contents lists all materials that appear in Atomnaya gnergiya. Those items that
originated in the English language are not included in the translation and are shown enclosed in brackets.
Whenever possible, the English-language source containing the omitted reports will be given.
Consultants Bureau Enterprises, Inc.
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ACCELERATION OF He3 UP TO 35 Mev IN ,THE ONE AND ONE-HALF
METER CYCLOTRON
N. I. Venikov, G. N. Golovanov, V. P. Konyaev,
N. V. Starostin, and N. I. Chumakov
Translated from Atomnaya Energiya, Vol. 11, No. 3,
pp. 213-216, September, 1961
Original article submitted January 30, 1961
A method is described for accelerating Her to 35 Mev ma cyclotron. A beam of 301a with an
energy spread of ?0.3% was obtained on a target 12 m from the cyclotron. Due to the use of a gas
recycling system, the loss of He3 was decreased by two orders and was approximately 5 cm3/hr.
Lately there has been great interest in the utilization of accelerated He3 nuclei as bombarding particles. There
have been reports concerning He3 acceleration in the Los Alamos [1] and Birmingham [2] cyclotrons. Until the present,
there have been no attempts to accelerate He3 in Russian cyclotrons. In usual cyclotron operation, where the amount
of running gas pumped out of the vacuum chamber and exhausted to the atmosphere reaches 0.5 liter/hr, the expendi-
ture of He3 is very great. In order to use the available supply of gas repeatedly, a special gas recycling system was
developed by the authors and used on the cyclotron of the I. V. Kurachatov Order of Lenin Institute of Atomic Energy.
The Gas .Recycling System
A diagram of the gas recycling system is given in Fig. 1. Gas is pumped from the cylinder by a special mercury
pressure regulator of the automatic-acting pump-type into the system to a pressure of 100-200 mm of Hg. Then the
cylinder is cut off and the gas is bled through a needle valve into the ion-source discharge chamber. Gas flow to the
cyclotron could be adjusted remotely from a control panel by a servomotor system.
Diffusion pump
Vacuum gauge no. 1
Needle
valve Vacuum gauge
number 2
Forevacuum pump
Oil vapor trap
Fig. 1. Diagram of the recycling system.
Charcoal
traps
Mercury
vapor trap
Mercury
pressure regulator
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On entering the cyclotron vacuum chamber, a small amount of the gas will be lost through nuclear reactions
and sorption on the chamber material. However, the main part of the gas is pumped out along with other gases by
the two diffusion pumps followed by mechanical forevacuum pumps. The pumped gas-vapor mixture proceeds
through a system of traps, is compressed to the required pressure and returned to the system with the pure He3.
One trap, which is chilled by liquid nitrogen, freezes out easily condensed substances (oil, water, and outgasing
products). The second trap, which is designed for the absorption of nitrogen and oxygen, is filled with activated char-
coal and also chilled with liquid nitrogen. There is also a trap for mercury vapor from the pressure regulator.
The charcoal trap's absorption capacity is 10-15 liter of air at normal pressure, consequently the service period
of such a trap with the usual vacuum system* leak rate, approximately 0.1 cm3/ min, is several days. When a
pressure increase in the system warns of a decrease in the charcoal's absorption capability, it is possible to switch to
a previously readied second charcoal trap of the same type. Preparation of the pump for service is accomplished by
heating it to 200?C for several hours in a special electric furnace while simultaneously pumping on it, with forevacuum
pumps. There is a reserve mechanical pump in the system also.
In order to reduce He3 losses on dismantling the system and with certain other operations (such as switching from
one pump to another), the dimensions of the separate parts of the system have been reduced to a minimum. The chief
harmful volume (the exhaust chamber of the mechanical pump) was significantly diminished by a fiberglas ballast in
the pump's exhaust chamber.
An additional careful packing of the mechanical pumps was carried out and a special water-cooled oil baffle
was introduced to decrease the oil entering the system with the He3 from the mechanical pump. The mercury regulator
supplied gas from the cylinder to make up the losses. The average loss of He3 during the experiment was about
5 cm3
/hr at atmospheric pressure.
5
030
?
40 50 60 70
R, cat
Fig. 2. Ion current dependence on the acceler-
ation radius.
Acceleration of He3
The maximum possible energy of the accelerated He3 ions
in the cyclotron was determined by the highest resonance fre-
quency attainable, 11.2 Mc. This frequency corresponds to a mag-
netic field intensity H = 11,000 oe. The ultimate energy of the
twice ionized He3 ions in this case is about 35 Mev at the 67 cm
radius.
00
I
50 u,kv100
Fig. 3. Target ion current de-
pendence on the deflecting sys-
The magnetic field was shimmed to secure adequate ver- tern potential.
tical ion focusing and so that the potential difference between
the dees was 160 kv (i.e., it was lower than the breakdown voltage). A pulsed ion source supply was employed which
increased the output of twice ionized helium by three-five times.
To decrease the ion losses during their acceleration and exit from the magnetic field, a focusing diaphragm
was designed and employed on the dees which on the one hand strongly increased the ion focusing along the vertical
? The volume of the cyclotron vacuum system is about 5000 liter.
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100 150 200
? 211,kv
Fig. 4. Target ion current depend-
ence on the dee potential difference.
in the cyclotron's central plane (where magnetic focus-
ing is practically absent)* , while on the other blocked
undesirable ions which in any case would have been lost
during acceleration and exit. This decreased the load on
the high frequency oscillator, reduced ion losses and con-
sequently also the background and induced activity. The
ion source was displaced to a previously calculated dis-
tance from the center of the magnetic field. The ion
current dependence on the acceleration radius is given
in Fig. 2. It is obvious from the figure that there are no
ion losses beyond a 40 cm radius. The ion delivery co-
efficient from the deflecting system was 7050.
To deflect the ions, a system was designed em-
ploying hyperbolic electrodes which permitted beam
focusing in the horizontal plant [4], more precisely,
which compensated for the defocusing action of the bend-
ing magnet's field. Similar systems to improve ion
beam parameters have been used in other acceleration
systems.
z,
3
2
0
-1
-2
-3
j, Relative units
-3 -2 4 0 1 2 3 x,cx
a
05 I j,relative units
Fig. 5. Ion current intensity distribution at the target
along the horizontal (a) and vertical (b) distance from
the target center: x along the horizontal; z along
the vertical.
Figure 3 shows the target ion current dependence on the deflecting system potential and Fig. 4 the dependence
on the dee potential difference. The following parameters were obtained for the Her ion beam at the target situated
12 m from the cyclotron: Hes ion energy, measured by the range in aluminum, was 35 Mev; half width of the beam
energy spectrum, measured by a magnetic analyzer ? not more than ? 0.31o; beam half width in the horizontal plane
at the target ? 8 mm, in the vertical plane ?less than 8 mm.
The ion current intensity distribution at the target along the horizontal and along the vertical is given in
Fig. 5. The average ion current intensity at the target was 30 jia. Usually work had been conducted with an average
target current of 10 pa.
Using the third subharmonic of the high frequency, a sizeable Her ion beam with an energy of 5.4 Mev was
accelerated and extracted on the target. To do this it was necessary to alter the potential between the dees (without
changing the resonant circuit tuning) and to decrease Ho to 10,000 oe. This result shows that subharmonic acceleration
does not drastically reduce the accelerated ion current.
The authors wish to express their deep appreciation to N. A. Vlasov and S. P. Kalinin for the continuing in-
terest in the project; to V. I. Lamunin and N. N. Khaldin for constructing the gas recycling system; to N. V. Kartashov
for tuning the pulsed ion source; to the staffs of the operating group and machine shop who assisted in the preparation
of the apparatus and cyclotron inlet system.
? A similar diaphragm is described in referente [3].
859
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LITERATURE CITED
1. H. Wegner, W. Hall, Rev. Scient. Instrum., 29, No. 12, 1100 (1958).
2. I. Sremlin, W. Hardy, H. Shaylor. J. Scient. Instrum., 36, No. 9 390 (1959).
3. A. Morton, W. Smith. Nucl. Instrum. and Methods, .f L3 (1959).
4. A. A. Arzumanov, E. S. Mironov, Atomnaya Energiya 6, No. 2, 202 (1959).
860
All abbreviations of periodicals in the above bibliography are letter-by-letter transliter-
ations of the abbreviations as given in the original Russian journal. Some or all of this peri-
odical literature may well be available In English translation. A complete list of the cover- to-
cover English translations appears at the back of this issue.
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SILICON COUNTERS FOR NUCLEAR SPECTROMETRY
S. M. Ryvkin, L. V. Maslov, 0. A. Matvee, N. B. Strokan
and D. V. Tarkhin
Translated from Atomnaya E-nergiya, Vol. 11, No. 3,
pp. 217-220, September 1961
Original article submitted March 18, 1961
Laboratory models of surface-barrier and diffusion-type silicon n-p counters were developed which
were suitable for nuclear spectrometry. The counters have linear pulse height-energy dependence for
particles with 60 i paths (in particular, for a-particles with energies up to 10 Mev), and ^, 0.5 To reso-
lution for an E of 5.5 Mev (with units of small area).
A series of papers [1-4] appeared in foreign publications during 1960 in which spectrometric counters of nu-
clear particles based on silicon n-p junctions were described. The semiconductor n-p counters operate on the prin-
ciple of the ionization chamber, but the pulse resolution of the best units exceeds the resolution of an ionization cham-
ber, being 0.25% or 14 key for 5.5 Mev a-particles [3,4]. Among other qualities of n-p 'counters, there should be
noted the relative insensitivity to magnetic fields, the small size, the reliable detection of strongly ionizing particles
in a background of weakly ionizing particles (for example, fission fragment nuclei in a background of a-, a -, and
y -radiation), the linear dependence of pulse height on energy, and the high counting rate.
Ru
n-SI
Fig. 1. Construction of a semiconductor counter and
circuit diagram (shaded portion ? space-charge re-
gion of n-p junction, the sensitive layer).
Fig. 3. External view of the Physico -technical
Institute counters.
Fig. 2. Oscillogram of Pu238 a-pulses (0.2 ?sec
markers).
The sensitive layer of the counter ? the space-charge
region of an n-p junction ? is formed in the immediate
neighborhood of the irradiated surface. The original sili-
con can be of either the n- or p-type. In the first case,
a film of gold several hundred atom layers thick is de-
posited to obtain an n-p junction; in the second case,
diffusion of phosphorus produces an n-region 0.1-1? thick.
These counters are schematically represented in Fig. 1.
Particles incident on the counter give rise to ioni-
zation, creating electron-hole pairs. These pairs are se-
parated by the field in the space-charge layer, and the re-
leased ionization charge Q is collected by the layer capacitance C and assembly capacitance Cm. Through this, the
capacity is charged to a potential difference
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(1)
861
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C,nti cm2
1200
1000
800
600,
400
200
0 5 10 15
20
25 30 v
0;02/01,arb units
7,2
0,f1
0,6'
0,4
0,2
AL:2 I, 5
L. fa
0
02/07),
E2=8,78 mev
E =6,05 Inev
10
Fig. 5. Dependence of pulse height and ratio of pulse
heights on applied voltage for a-particles with ener-
Fig. 4. Dependence of counter capacity on applied gies of 8.78 and 6.05 Mev.
voltage (unit numbers: 0 ?103; ? ? 90).
20
30
40
50 v
Better peak resolution is obtained when practically the entire particle track is contained in the space-charge region
the depth d of which is determined by the relation
d = 1,4.10-6 V (Vo+ QIL Cht,
(2)
where V0 is the contact potential difference of the n and p regions (v); V is the applied bias voltage (v); p is the
specific resistance of silicon (ohm-cm); II is the current-carrier mobility (cm2-v-sec).
The characteristics of counters which were developed during 1960 at the A. F. Ioffe Physico-technical Institute
of the USSR Academy of Sciences are described in this paper.
Small area counters had a pulse height --lmv/Mev and a resolution of less than 110 for Ea = 5.5 Mev. The
pulse shape is shown in Fig. 2. The counters were made by deposition of gold on n-type silicon and by diffusion of
phosphorus into p-type silicon. The working area of both types of counters had values of 2 x 2, 5 x 5, and 10 x 10
mm (Fig. 3)
In what follows, results of the investigation of the following counter characteristics are presented: 1) voltage-
current characteristics; 2) dependence of capacity on bias voltage; 3) pulse height; 4) dependence of pulse height on
a-particle energy; 5) resolution.
1. The voltage-current characteristics of the units have the usual shape for n-p junctions. The inverse current
was 0.5-0.05 a at 40 v for a group of units 2 x 2 mm2in area. For units with 5 x x and 10 x 10 mm2areas, the
current increased in proportion to the area. The breakdown voltage varied from 50 to 60 v.
2. An important parameter of the counter is the capacity of the sensitive layer ? the space-charge region. In
the first place, the magnitude of the capacity determines the pulse height; in the second place, it is easy to determine
the thickness, d, of the sensitive layer from the value of the capacity. It is obtained in a manner similar to that for
a plane condenser
d 8?8
4nC '
(3)
where S is the area of the unit; E0 is the dielectric constant. Since d V + V? :he capacity must decrease as
(V + V0) -1 with increase in applied voltage. This dependence was fulfilled with satisfactory precision by our units.
The dependence C = f (V) calculated for a unit 1 cm2 in area is indicated by the solid line in Fig. 4.
3. Pulse height for a given capacity is determined by the free particle charge Q = eN where N is the number
of ion pairs which, in turn, is determined by the average energy for pair formation (E) and the energy of the ionizing
particle. In previous work (for example, [4]), it has been established that E does not depend on the nature and energy
862
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? Not
200
150
100
50
0
5,491
Mev
Generator
4ikey
?
? I
? 0
40key .

30kev
t
I I
I 1
I
?I 1
.
II
11\
/ ?
/
/
.
.
40 50 60
channel number
70
Fig. 6. Pulse height spectrum of Pu238 a-particles (Peak half-
width after subtracting instrumental noise was 27 key or 0.5010
of the ionizing particle, and has a value ?3.5 ev for silicon. For Pu 238 a-particles, we obtained Q = 2.5.10'13 k, i.e.,
6 = 3.53 0.15 ev, with our counters. Therefore, charge was collected just as completely as in counters described
earlier.
4. It follows from formula (1) that pulse height is proportional to charge collected. Therefore, by irradiating the
counters with a-particles of different energies, and collecting all the resulting charge, we ought to obtain a linear
dependence of pulse height on particle energy. Since a-particles with different energies have different path lengths,
one should expect that complete charge collection will occur for different sensitive layer thicknesses, i.e., for different
voltages. The dependence of the pulse height (I, on counter voltage V is shown in Fig. 5 for a-particles with energies
of 8.78 and 6.05 Mev. It is clear that pulse height reaches a saturation value for the short-path group at ? 15 v.
However, in this situation, the thickness of the sensitive layer is still insufficient for complete collection of the charge
created by the more penetrating particles with an energy of 8.78 Mev. Saturation is achieved at ? 35 v for the more
penetrating group. In addition, the ratio of pulse heights is equal with great precision, to the ratio of energies which
testifies to the linear dependence of .1)(Ea). We were unable to check linearity for higher energies, but one can predict
that linearity will be maintained at V = 60 v for a-particles with energies up to 10 Mev, or for other particles with
6011 paths.
5. We studied the value of peak resolution by standard methods using a 100-channel analyzer. Signal distortion
because of noise and instrumental instability was taken into account with the help of a pulse generator. The spectrum
of Pu238 a-particles measured with a 2 x 2 mm2counter is shown in Fig. 6. From the figure, it can be seen that two
groups of a-particles were resolved whose energies differ by 41 key. The absolute value of the resolution after
allowing for instrumental noise was 27 key or 0.501o. It is necessary to point out that the resolution depended strongly
on the area of the unit. Thus, for 5 x 5 mm2 counters, the resolution was 101o, and for 10 x 10 mrr? counters, 10010 .
Such a dependence is apparently explained by the fact that the characterisitics of various portions of a large surface
will be non-uniform because of the non-uniformity of the silicon used, leading to a spread in pulse heights. Units
10 x 10 mrr in area prepared by us were used also at the Joint Institute for Nuclear Research in Dubna for detecting
863
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Ncr,f
150
100
50
0
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13
0
12 20 28 36 44 52
channel number
60
Fig. 7. Pulse height spectrum of U2SS fission fragments in
the presence of cc-particle background of 104 sec-1.
864
fission fragments from Um in the presence of a high
a-particle background (104 sec-1). The resolution of
two main groups of fragments is clearly demonstrated
in Fig. 7 which was kindly furnished us by our associates
in the laboratory of G. N. Flerov, corr. mem. Acad.
Sci. USSR. The voltage on the unit needed for reducing
a-particle pulse heights while taking the spectrum was
not given.
The results presented in this paper on the counting
of a-particles and fission fragments do not exhaust all
the possibilities for counter development. For example,
n-p counters can be used for counting fast and slow neu-
trons if nuclear reactions with neutrons which form heavy
charged particles are employed.
The authors consider it a pleasure to thank engineer
G. V. Khozov, technicians I. A. Lebedeva and G. D.
Gusarina, and machinist P. I. Gorshkov for helping greatly
in this work.
LITERATURE CITED
1. J. Blankenship, C. Borkowski, Bull. Amer. Phys.
Soc., ser. 11, 5, No. 1, 38 (1960.
2. S. Friedland, L. Mauer, J. Wiggins, Nucleonics,
18, No. 2, 54 (1960).
3. J. McKenzie, J. Waugh. Bull. Amer. Pbys. Soc.,
ser. II, 5, No. 5, 355 (1960).
4. M. Halbert, J. Blankenship. Nucl. Instrum. and
Methods, 8, No. 1, 106 (1960).
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TWO-DIMENSIONAL BOUNDARY PROBLEM FOR TWO-DIMENSIONAL
SQUARE LATTICES ?
L. Trlifai
Institute of Nuclear Studies, Czechoslovakian Academy of Sciences, Prague
Translated from Atomnaya Energiya, Vol. 11, No. 3,
pp. 221-229, September 1961
The present article is concerned with the density distribution of thermal neutrons on the surface of lumps in two
semi-infinite two-dimensional square lattices that are separated by a plane. The solution of this problem can be re-
duced to the solution of the Riemann boundary problem, which can be expressed in closed form. According to an
analysis of the approximate solution for cases of practical importance, the asymptotic neutron density and its deri-
vative are continuous at the boundary if the lattices are replaced by a homogenized medium. A similar solution of
this problem for a lattice with an infinite reflector (moderator) is considered.
Introduction
In calculating a multizone heterogeneous reactor,it is necessary to determine the conditions for the neutron
density at the boundary between two zones or at the boundary between the reactor core and the reflector. If the
dimensions of individual zones and the curvature radius of the boundary are large, the necessary conditions can be
determined by solving the problem of the neutron density distribution in two infinite lattices which are separated by
a flat boundary.
For the sake of simplicity, we shall assume that both lattices are square, that the spacing is a, and that the
boundary betw6en the lattices, is equal to the distance 8./2 from the boundary lumps of both lattices. The lumps are
cylindrical, unbounded, and located at the nodes of the lattices. If we use the assumptions of the heterogeneous method,
which has been developed by A. D. Galanin, S. M. Feinberg, et al., the thermal neutron density N(ka) at the surfaces
of lumps will be determined by the equation [1].
(I + po)N (ka) =-- 1-1 0 (I k ? I a) N (le a) +
co
? H
h =-0 (1 k ? a)for k < 0;
'
-1
(1 + pi) N (ka) E H 0 (I k ? I a) N (lea) -I-
CO
? H (I k ? k' la) N (k' a) ;pm k> 0 , (lb)
h'=o
where
and
a
240j
I (I k I a) =
Ikla)
[ exp ELIO ?
ati
a
exp CEO S X
2 Vagoi
dx
X ?= exp ? x
x
qii a2
P qoj 12L2q01
*This article has been received from the Czechoslovakian Socialist Republic.
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(2a)
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for j equal to Oar 1.
In Eqs. (la) and (lb), it is assumed that the symmetry is such that the neutron density is equal in all lattice
nodes that lie in a plane parallel to the lattice boundaries. These nodes are characterized by the integer k. The
lattice with type-1 lumps fills the half space with k a 0, and the lattice with type-0 lumps fills the half space with
k < 0. The properties of the moderator are characterized by the moderation length Tr and the diffusion length L.
The constants qoj and qij denote the internal and the external lump effects in lattices with type-0 and type-1 lumps,
respectively; ij j is the effective value of the number of secondary neutrons in lump j.
From physical considerations, it is clear that, at a certain distance from the boundary between the lattices, the
solution N(ka) of Eqs. (la) and (lb) in both lattices approaches the asymptotic solution A. (ka), which is determined
by the equation
(1 p j) A (ka) =
(3)
= H (I k ? k' I a) A j (k' a)
for j equal to 0 or 1.
The general solution of Eq. (3) is well known (1]; it contains two constant factors, the values of which are not
determined. However, in the case under consideration, the asymptotic regions are connected with the boundary re-
gion, so that only two of the four constant factors in Eq. (3) will be independent. The elimination of these two in-
determinate constants leads to the boundary conditions for the asymptotic curve of the thermal neutron density; the
determination of these conditions is important in heterogeneous reactor design. The derivation of equations on the
basis of the above considerations is given below.
Let us break up the solution N(ka) of Eqs. (la) and (lb) into two portions:
N (ka) A (ka)
N (ka) = A1 (ka)
n, (ka) for
n, (ka) for
k < 0;
k>0.
t (4)
The ni (ka) values play a more important role only in the boundary region, while, with an increase in I kl , their
absolute value drops very quickly (for instance, it drops more rapidly than the value of 13 exp (- I k I a), where a
and 6 are positive numbers). According to expressions (la), (lb), and (3), the values of nj (ka) satisfy the following
equations:
866
(1 + p o) no (Ica) = k! Ho(ik ? I a) no (le a) +
=--o0
Hi(lk?kila)ni(ea)d-
k'=o
(5a)
+ hO [i I 1(1
a) A1 (k' a)
? H k ? 17) Ao(ka)];
(1 + 131) n1 (Ica) = H 0(1:1c ? I a) n (le a) ?
? HIP ? k' I a) n, (k' a) +
?1
+k E ["(I["(Ik ? I a) A, (k' a) ?
'=?oz)
? 1/1 k ? k' I a) A, (k' a)].
(5b)
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I. Reduction of Equations (5a) and (5b) to the Riemann Problem
Since the values of nj (ka) decrease fairly quickly with an increase in I kI , we can determine functions 013+(z)
and 61)- (z) of a complex variable z whose values on the unit-radius circle K with the center at the coordinate origin
are determined by the following series:
00
(s) sh n1 (ka);
lx.= 0
-1
(s) sh no (k a) .
, it?co
(6)
Since the points s are located on the unit-radius circle, it can be assumed that s = exp(iaw). Thus, relationships (6)
can be considered as Fourier series for the function of the (real) variable w with the period 2r/a of the inverse lattice.
After multiplying Eqs. (5a) and (5b) by sk and performing summation with respect to k according to expression
(6), we obtain after certain transformations:
[1 p ? F i(s)] (s) =
= +Po ? F 0 (8)1V (s) S (s)
for s = exp (iaco),
where
and
S (s) = SJo [H1(1 k k' I a) A1 (k' a) ?
? H0 (l k k' la) A0(k'a)]-1-
co ?1
+ Ash co[ ? H (I k k' I a) A1 (k' a) +
+H 0(J k ? k' la) Ao (k' a)].
(s) =h c2co kl a)
(7)
(8)
(9)
We shall find two functions of the complex variable z which satisfy the linear relationship (7) on a circle with
unit radius, namely, the function cl)+(z), which is an analytic function in the inside region K- of the circle K, and
the function 4)-(z), which is analytic in the external region K- of the same circle, including z = CO. Then, the sub-
sequent solution of E. (7) will be reduced to the solution of the nonhomogeneous Riemann boundary problem. In this,
we shall follow the terminology and notation used in [2].
In order to solve the Riemann problem, it is necessary to determine the form of the function S(s) in Eq. (7), which
is determined by expression (9), where A(ka) are solutions of Eq. (3). As was mentioned before, the solution of Eq.
(3) is well known [1]. With the accepted notation, we can write:
A (ka) = A .? B z7h
.71 :71 I
where A? andB ? are constants, and z? is the root of theequation
l
(10a)
1+ pi ? (zi)= O. (10b)
The F3 (z) function is expressed by the Laurent series (8). For an active medium, zj = exp(iK ja), while, for an inactive
medium, zj = exp (K ja), where K j are real parameters [3]. For a critical medium-, Eq.(10b) has a double root which
is equal to unity, and the corresponding solution of Eq. (3) will be given by A3(ka) = Aj + Bjka.
The summation of the series in expression (9) is given in the Appendix (see end of article). The obtained re-
sult can be written in the following form:
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S (s) = (- 1)5.1 + pj? Fj 5)] x (11)
j=0
X (?I IA.+ B
sz ? 2 S-Zi 2 ?
After dividing both sides of Eq. (7) by 1 +Pi _ Fi(s), we obtain the usual form of the Riemann problem. The
coefficient of this problem and its free term [2] satisfy the Helder condition on circle K, with the exception, perhaps,
of the points zi and zi-1. At the points zo and 41, the coefficient of the problem may be equal to zero. From this
point of view, the following three cases are of interest.
1. Media 0 and 1 are Active. In this case, we can write Eq. (7) on the circle K in the following form:
G (s)cir (z) ? g (s).
82?(z,+-4-)s-1-1
The G(s) coefficient is real, bounded, and different from zero on the circle K, since, according to Eq. (7),
and, according to (8),
[1-1?po?F0 rs2?(zid?n s+11
G (s)?
[1+ pi?F2
F5 (s) = F (4-) = F7 (s).
The index of the coefficient G(s) is then equal to zero. The free term g(s) in expression (12) is equal to
g(9= 1G
z s
0
jr)
-FB0(zo
+B (z--)}
and it has poles at the same points as the coefficient in front of 4)-(s) in expression (12),
of the free term poles does not exceed the order of magnitude of the poles of this coeffic
The Riemann boundary problem of this type has been solved in [2], and, therefore,
results. The solution has the following form:
868
(s)
(s)(s) + (.5));
82 ? s +1
(12)
(13a)
(13b)
while the order of magnitude
ient.
we shall write only the final
(14a)
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1(s)
iD (s) ? (s)+ P1 (s)1,
s2 ?(zo+ s +1
X? (s) = exp (r? (s)),where r? (s) =
= ? -T In G (s) 2:11i Int G s(t) dt;
(14b)
g
1 1 'N g (s) = [ s2 ? (zi s (s) (14c)
21ni [ t2 (zi ;10 t Vtit) tdt s.
k
The function Pi(s) is a first-power polynomial with indeterminate coefficients. In system (14), this function represents
the solution (12) of the corresponding homogeneous Riemann problem. The power of the polynomial is determined
in such a manner that 4'-(z)--,0 for izI -4 .0 in correspondence with expression (6). The integrals in system (14) are
considered as Cauchy integrals.
If we know rI3+(s) and .1)-(s), we can determine the values of nj(ka). According to expression (6),
no (ka) (s)
(15)
for k < 0; ni (ka)
dss-h-10+ (s) fOr k> 0.
The expressions under the integral sign in these equations must be functions that can be integrated. In correspondence
with Eqs. (14a) an d (14b), this can be secured by putting
(s)d- Pi (s) = 0 for s equal to z and 1 ? ,
and ir (s)d- P1(s) = 0 for s equal to zoand_ (16)zio
Moreover, the thermal neutron density and the other physical parameters must be real quantities, and, consequently,
the expressions (15) for n(ka) must also be real. On the basis of expression (15), it can readily be shown that this
requirement is satisfied if the coefficients of the polynomial in system (14) are real. On the basis of the same con-
siderations, we must assume that, in the case under consideration, Bj = A , where the asterisk denotes a complex
conjugate quantity.
Thus, the thermal neutron density on the surfaces of lumps can be expressed by means of Eqs. (14), (10a), (10b),
and (15). The corresponding expressions contain six constant real numbers (ai = Ai + Al, bi = i(Ai + Al). where j
is equal to 0 or 1, and two real coefficients in P1 (5). These constants are related by the four conditions (16), i.e.,
only two out of the six constants are independent. For the independent constants, it is convenient to choose aj and
bj, which pertain to the asymptotic density in the medium j; the asymptotic in the medium j j, i.e., a'i and bij.
will then be determined. If, in the asymptotic density Aj (ka), we use continuously varying coordinates by means of
the substitution ka-4. y, the independent constants aj and b.; can be eliminated, and we can obtain the boundary con-
ditions for homogenized media, which relate the asymptotic thermal neutron densities to their derivatives at the boun-
dary between the two media.
? We shall prove the latter conclusion by considering an example of lattices where neutron moderation does not
take place. The latter assumption was made in connection with the fact that we have still not succeeded in deriving
from Eq. (15) any simple analytic expressi on for the general case. In this case,
Fi (z) = ? ?a Lq(,) \ exp ( ?T) ? 1 x
.L2
sin hL
a (17)
X
a
z+ --2 cos h L
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i.e., according to Eq. (13a), G(s) = -(1+P,)/ 1 + Ps. The integrals in expression (14c) can now readily be determined
by using the Riemann formula:
1
--2T (zjX (s) ==t;
X+ (s) = I -1-P? ; T-(s) -,------ 0;
l+p,
W+ (s) = ? ao (1 ?s cos x0a)
be sin x a 1+ PI X
0 1+ po
Xi? (1? S cos xla) ? bis sin xsa].
(18)
From the second of conditions (16), it follows that Ps (s)a-0. By using the first of the conditions (16), we shall de-
termine the values of ao and bo in dependence on as and 131:
1+ps , l+ps
ao=i+ vo--i?p X
Po
X
cos xoa ? cos xsa a, + sin xla
bs)
sin xoa sin xoa
(19)
However, for these ao and 130 values, 11,4- (s)---0. According to expression (15), this means that the asymptotic solution
(y) ai cos x3y bi sin xiy, (20)
where y = ka, while the ao and 130 values are determined by Eq. (19), is the exact solution of the problem. Considering
y as a continuously changing variable, we can express the independent constants as and 131 in terms of the values of
functions A(y) and their derivatives A'j(y) at certain points y j:
A1 (y1) cos xiy, ? A; (ys) sinxxiiyi = al = 11++ Z [ A, (y,) cos x0y, A' (y,)
cos xiYi. b sin xoyo 1 .
xo i' (21a)
A, (y1) sin xiy, + A'? (Ys) 1? (21b)
xs
_1+ po r cos xo (y0+ a) ?cos xoy, cos xla sin x, (yo + a)? sin xoyo cos x,a1
1+pi L A (1 (g o) sin xia + A; (Y 1) x, sin xia i ?
These relationships express the boundary conditions for the homogenized media 0 and 1 for certain definite yj values.
The most rational choice will be yo = Ys - a/2. The boundary conditions (21a) and (21b) then assume the following
form:
870
+ po)tosy A0(
(I+ P?) sin, Ao' (? 22-)?
xo
2 2
(22)
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Since the relationships (1 ? pj) x cos kja /2 1 and (1 + pj) K j-1 Sinki a /2 IN a/2 hold for lattices that are usually
encountered in practice, conditions (22) signify that the thermal neutron density and its derivative are continuous at
the boundary. It seems to us that this statement will also remain valid in the case where the moderation of neutrons
is taken into account if only the type-0 and type-1 lattices do not greatly differ from each other with respect to
their physical properties.
2. Medium 0 is Inactive and Medium 1 is Active. Equations (7) and (11) can be written in the following form:
D+ (s) = G(s) Cr (s) g (s),
C1 ) 1
82?(zi-1-71.- 8+
where
G(s)=
and
rs+ I [Id-po?F0(s)]
1+ F (s)
I
g (s) = X
s 11-.) +1
(szof 1A0+ szozoB0)+
X [G (s)
(23)
(24a)
(24b)
The index of the coefficient of G(s) is equal to unity. The solution of the corresponding Riemann problem is ex-
pressed by means of the equations [2]
(s) X+ (s) (s)+C]
sz?(k)s-1-1
and 0- (s) = X- (s) [T- (s) d- C],
where
X+ (s) = exp Er. (s)], X- (s) = s-1 exp [F- (s)],
F(s)= [s-IG (s)] + I .in [t-1G (t)] dt?
2rct t?s
111.1 (s) = [S2? (Zi S+ 1 Vs()s)-E
g (t) 1
1 +\
27-ti dt [t2 ? (z1+? + 1]
(25a)
(25b)
The symbol C denotes the constant which must be real (C = Ce).
kThe values of ?( a) are determined by using Eqs. (15), in which (1)+() must be a function that can be integrated,
we assume that
(s)+ C = 0 for s equal to z and? .
(26)
If we now calculate all constants that were not determined up to now, we obtain five real constants in the problem:
C, Ao, Bo, a1 = A1 + Al* , b = i (A1? A11). According to conditions (26), we shall eliminate two of these constants,
which will leave us with three independent constants, which contradicts the physical considerations. This contradiction
can be eliminated in the following manner. Since the first portion of the asymptotic solution (10a) corresponds to
an inactive Medium 0, i.e., Aoexp( + Koka)(K 100 Bev in cosmic
rays point to an approximate constancy of total cross sections of strong interactions, in any case in the energy range
up to 106 Bev. However, it should be noted that errors in the measurements reach very high proportions, and that
experimental data do not exclude a very slow increase or decrease in cross sections. Over the entire energy range
stretching from several Bev to 106 Bev, 800/0 of all the particles generated are 71 -mesons; the mean transverse momen-
turn and optimum energy value of particles being generated in the center-of-mass system also remain constant and
independent of the energy of the primary particle. The mean number of particles generated varies approximately as
the fourth root of the energy of the primary particle. The coefficient of inelasticity for very high energies is about
0.2-0.3. These problems were the subject of a review report presented by D. Perkins.
The results found in cosmic rays were also discussed in reports by Polish physicists M. Miezowics and J. Herjul.
The investigations of multiple particle production at very high energies, carried out in Poland, and especially the
investigation of open angular distributions with two maxima (the so-called two-humped stars) performed by the Polish
physicists led to the conclusion that the principal features of inelastic interactions at very high energies may be ac-
counted for by assuming a dual-center generation of secondary particles.
The attention of the conference was also attracted to a paper by B. M. Pontecorvo and Ya. A. Smorodinskii on
the relation between the neutrino and astrophysics. Calculations have demonstrated that available experimental
data are not in contradiction with the hypothesis holding that the energy density associated with neutrino and anti-
neutrino fluxes is larger by many orders of magnitudes than the energy density associated with apparent matter through-
out the universe.
G. Cocconi and G. von Dardel reported experimental results obtained with the new large CERN accelerator.
Data on total cross sections had been published earlier. New results referred primarily to ir -p-interactions at 16 Bev
and p-p-interactions at 24 Bev. These findings do not differ qualitatively from those obtained at Dubna for it -p-inter-
actions at '7 Bev and p-p-interactions at 9 Bev. In particular, secondary particles in the center-of-mass system have
sharply anisotropic angular distributions. It was stressed that the mean transverse momenta of generated particles of
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different species remain more or less constant independently of the species and energy of the colliding particles. This
constancy of transverse momenta is observed over the entire presently accessible range of high energies.
In his report, G. Cocconi also discussed some interesting data on quasielastic p-p-scattering at 24 Bev. During
measurements of momentum distributions of protons scattered at very small angles, .a maximum which might be
interpreted as due to resonance interaction between an intermediate it -meson and a target proton in the 3,3-state was
detected, in addition to the usual maximum corresponding to elastic scattering. Some experimental indications point
to the existence of two additional maxima corresponding to two successive resonances in it -N-interactions.
A review of statistical theories of inelastic interactions at energies -.30 Bev formed the subject matter of papers
by R. Hagedorn and E. Sudershan. It was noted in both reports that the various variants of statistical theories usually
employed for calculation of multiple production of particles are suitable for explaining only averaged, global char-
acteristics of inelastic interactions. For example, distributions of stars by multiplicity, probabilities of various channels
of inelastic reactions, and mean momenta of particles generated are close to their experimental values. However,
everything pertaining to angular distributions is in sharp contradiction to experimental evidence. This is apparently
precisely what is invoked, in particular, to explain the pronounced divergence, noted by R. Hagedorn, between theo-
retical and experimental probabilities of antinucleon formation at various angles in p-p-collisions at 24 Bev. At the
limits of applicability in each case, several variants of the statistical theories yield close results and prove to be
highly useful for calculating beams and planning experiments.
A special session was devoted to a discussion of diffraction phenomena in strong interactions. The results of
calculations of elastic -N-interactions observed at Dubna were reported on in a paper presented by D. I. Blokhintsev.
,It was shown that the real part of the amplitude of elastic it -N-scattering at high energies ( >1 Bev) is much smaller
than its imaginary part; the distribution of nuclear matter in the nucleon and the nucleon radius were computed; a
new method for analysis of diffraction scattering, which is in some cases preferable to the more familiar optical model,
was proposed.
The phenomena of diffractive particle production were discussed in a detailed and exhaustive report by M. Good.
It is generally known that the theory of such phenomena was first developed by the Soviet physicists A. I. Akhiezer,
I. Ya. Pomeranchuk, and E. L. Feinberg. At the present time, this theory has gained utmost urgency because of the
possibility of verifying it experimentally on the large accelerators now available.
G. Solzman delivered a review paper on single-boson peripheral interactions; the results of numerical calcu-
lations run on electronic computers at Dubna were reported in the paper by D. I. Blokhintsev. Experimental data
now available are not in contradiction to the assumption that the cross section of peripheral it -N- and N-N-collisions
is many times in excess of the cross section for central collisions, for which a purely statistical description is applicable.
The average numbers of particles produced, their angular and momentum distributions calculated under the assumption
of a purely single-meson process, are in excellent agreement with empirical experience, within the limits of ex-
perimental error.
The theory of peripheral interactions, which is a natural outgrowth of statistical theory, nevertheless remains a
very coarse theory. In particular, the virtuality of a peripheral meson is neglected in the calculations even at high
momentum transfers (-0.5 Bev). But the theory still fits satisfactorily with experiment in many cases, even when its
conditions of applicability are rather poor. It was noted in the discussion that the further progress of this theory de-
pends crucially on amassing fairly accurate experimental data to establish the points at which divergences between
theory and experiment occur.
The use of single-meson peripheral interactions to account for quasielastic p-p-scattering detected in 24 Bev
experiments was the subject of reports by F. Celleri and E. Ferreri, M. Baker, and B. Feld. Dispersion relations
techniques were invoked by the first two authors in calculating the pion-nucleon vertex.
The use of Mandelstam binary dispersion relations to calculate high-energy phenomena was discussed in papers
presented by S. Fraucci, S. Fubini and D. Amati, C. Goebel. This trend is one which has come into prominence
only recently, and most of the results here are of solely methodological interest; however some very encouraging
numerical results have also come to light. For example, angular distributions of ff--mesons scattered elastically
on protons at energies of 1.7 and 5 Bev, calculated by Fubini and Amati, are in excellent harmony with experiment-
ally derived values. Despite the crudity of the approximations used in the calculations, this undoubtably represents
considerable progress, since all calculations in this field have up to now been carried out solely on the basis of the
phenomonological optical model.
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A report delivered by H. Leman was devoted to an investigation of the asymptotic properties of the amplitude
of elastic scattering. It was shown that the real part of the amplitude is always considerably less at high energies
than its imaginary part, although the form of the energy dependence of the real part is dependent on concrete
assumptions as to the manner in which the total cross sections tend to their constant limiting values as energy increases.
These conclusions are in good agreement with results of computations carried out at Dubna. A considerable portion
of Leman's report was given over to an account of the work of V. A. Gribov and I. Ya. Pomeranchuk, who examined
the asymptotic behavior of the amplitude of processes involving particles and antiparticles in the ground state. It
was particularly emphasized in this paper that no exponential variation in the cross section such as predicted by
statistically theory was ever encountered. One should note, however, that all these conclusions are based on a re-
placement of a virtual meson by a real one. The results of Gribov and Pomeranchuk may conceivably indicate that
. such a replacement must be resorted to with great caution.
A report by A. Schock presented the parameters of now familiar proton accelerators extrapolated to energy re-
gions of the order of several hundred billion electron volts, and carried out a comparison of possibilities seen in
accelerators of the usual type and accelerating systems based on colliding proton beams. The conventional acceler-
ators will serve a broader range of purposes, apparently, from the standpoint of versatile experimentation.
Interesting data on electron accelerators with colliding beams were contained in papers presented by B. Tuszek
and B. Richter. Construction of an electron and positron colliding beam accelerator with particle energies of 250 Mev
In each beam is nearing completion at Frascati. The presence of one and only one storage ring is a feature of this
accelerator. Electrons and positrons are obtained via pair formation of gammas, which, are in turn generated by an
electron synchrotron.
The expected beam lifetime is ?250 his under 10-1? mm Hg pressure. At the present time, the storage system
has been completely assembled, and the first experiments on injection and storage of particles have been carried
out. At Stanford, construction is nearing completion on an electron beam stacking system at 500 Mev. It is expected
that the first experiments on elastic scattering of electrons by electrons will be successfully engineered in about one
half year.
Stress was laid time and again in the discussions and reports on the enormous importance of improved accuracy
of experimental data. This task is one of the most important and most urgent ones in contemporary high-energy
physics.
USE OF TRITIUM IN PHYSICAL AND BIOLOGICAL RESEARCH
Ya. M. Varshavskii and A. A. Ogloblin
Translated from Atomnaya Energiya, Vol. 11, No. 3,
pp. 264-267, September, 1961
A symposium devoted to, the use of the radioactive isotop of hydrogen ? tritium ? in physics, chemistry, and
biology, was held in Vienna during May 1961. The symposium was organized by the International Atomic Energy
Agency in collaboration with the Joint Commission on Applied Radioactivity of the International Union of Scientific
Societies. About 300 delegates from 28 countries and from four international organizations were in attendance.
The calling of this symposium on an international scale was completely justified by the already large and consistently
expanding interest in tritium. Tritium is the only radioactive isotope of hydrogen ? the element which enters into
?the composition of water and a large variety of other widely distributed and abundant chemical compounds, and also
into the composition of almost all substances forming living organisms. This has led to the recent extensive use of
tritium as a labeled atom in chemical and biological investigations. It is important to bear in mind that, of the re-
maining elements of vital importantce to chemistry and biology (i.e., oxygen, nitrogen, and carbon), only carbon has
a long-lived isotope, Cm, suitable for research ends. However, in contrast to tritium, pure CIA is virtually inaccessible
and the specific activity of CIA preparations is quite low (0.001 curie/mole), while tritium preparations have an
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activity of several curies per mole. This fact, added to the relatively low cost of tritium and tritiated compounds,
lends particular importance to tritium applications.
Since tritium readily displaces ordinary hydrogen in water, it has been possible to us tritium in various branches
of geophysics related to flow and movement of water, such as meteorology, oceanology, and hydrology. The study
of the problem of the origin of tritium on earth has revealed data of interest on cosmic phenomena.
Research related to the tritium nucleus, known as the triton, has assumed intense interest and led to applications
of practical importance. Triton is, following the deuteron, the simplest nuclear system, and the study of its interactions
with other nuclei has yielded a series of valuable information on the structure of nuclei and the mechanism of nuclear
reactions. The large cross sections of some reactions involving tritons at low energies and the large energy yields of
those reactions have made tritium one of the most important thermonuclear fuels.
All aspects of the use of tritium in various fields of natural science reveal many features in common, related
to the procedure for introducing tritium into the system being studied, detection of tritium, and consideration of
isotope effects due to the considerable difference in the masses of tritium and its light hydrogen counterpart, protium.
The papers delivered at the symposium may be arbitrarily broken down into two groupings, as follows: 1) methods
for detecting and recording tritium responses; 2) distribution of tritium in nature and its use in meteorology, ocean-
ology, and hydrology; 3) isotope effects of tritium; 4) techniques for introducing tritium into molecules of chemical
compounds; 5) use of tritium for the study of the mechanism underlying chemical reactions and radiation-chemical
processes; 6) the use of tritium as a tracer atom in the study of biological processes and the effect of intrinsic radi-
ation emitted by tritium on biological systems.
Methods for Detecting and Recording Tritium
The most precise technique for determining the amount of tritium 'present consists of measuring tritium activity.
Since the beta particles formed as tritium decays are very soft (6 -spectrum cutoff at 18 key, corresponding to a range
of 0.5 mg/cm2), the tritium has to be introduced into the operational volume of the counter in order for activity to
be measured. At the present time, two techniques for recording tritium emissions have been employed with success:
1) using a Geiger counter (less frequently a proportional counter) with tritium introduced in the gaseous phase into the
counter interior; 2) using a scintillation counter with a tritium-containing liquid scintillator.
The primary advantage of Geiger counters in this application is their high efficiency (close to 100%), although
they can be used to measure the activity of only a few specimens (since the entire specimen must be converted to
the gaseous phase). In most cases, preliminary enrichment of the specimen with tritium is necessary, introducing some
additional error into the measurements. The most important problem in the design of facilities based on Geiger
counters is therefore reduction of counter background and finding means of increasing the amount of tritium which
might gain access to the counter.
To reduce background, recourse is had to shielding against external radiation and to anticoincidence counters.
To reduce background attributable to radioactive contaminations of the counter material proper, the volume of the
counter used to record tritium emissions is sometimes separated from the volume of anticoincidence counters in which
it nests by a single thin foil. In the best counters reported on at the symposium, the background was 2-3.5 cpm for
an effective volume of 1.5-3 liters.
The amount of tritiated gas which can be accommodated in the counter is limited by a deterioration in counter
characteristics. An investigation of the quenching properties of various gases has shown that ethylamine yields the
best results. When the counter is filled with ethylamine to 3-7 cm Hg and with hydrogen to 40 cm Hg, very few spurious
counts are observed; the length of the plateau goes to 500 volts. Good results are also had with ethyl ether, isoprop-
ylamine, and isoprene. All of these gases yield excellent counter characterisitics superior to those of ethylene, the
standard gas used till now. Another very effective approach has been to supplement internal quenching by means
of a quenching gas medium with external quenching with the aid of an electronic circuit, which lengthens the counter
dead time to 10'3 sec.
Until recently, no success had been met in attempts to obtain satisfactory counter characteristics when a counter
was filled with water vapor to a pressure above 20 mm Hg. A paper by R. Ealey and L. Ballard (USA) described a
counter having a plateau over 200 volts in length when the counter was filled with water vapor to 350-400 mm Hg,
and with a mixture of butane and helium to 350-400 mm Hg.
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In contrast to Geiger counters, scintillation cowiters can be used with many specimens. However, the effi-
ciency in recording tritium radiation is not high for scintillation counters, in fact usually only several percent,
attributed to the low energy of decay. This efficiency has been successfully enchanced by the use of special multi-
plier tubes (J. Sharpe, W. Stanley, Britain).
The composition of the scintillator has an important effect on tritium counting conditions. In working with
tritiated water, as D. Beal and J. Whitehead (Britain) have shown, the best mixture is dioxane ? naphthalene ? water
with a water content of 18.6%. Difficulties often arise in work with organic compounds, because these compounds
either will not dissolve in the scintillator or because they quench the light flash. This explains why choice of the
proper solvent is one of the first problems to be tackled.
On the whole, the symposium evinced a certain tendency to give primacy to the role of Geiger counters over
that of scintillation counters. The best facilities using Geiger counters are capable of measuring a tritium concen-
tration of the order of 1 atom of tritium per 1016 hydrogen atoms. Scintillation counters remain most convenient for
rapid and not particularly precise determination of tritium content.
Problems related to recording of tritium nuclei formed in nuclear reactions were discussed in a paper presented
by A. A. Ogloblin (USSR). The technique developed in this case allows for measuring the energy and angular dis-
tributions of tritons under conditions practically free from background contributed by other charged particles. The
tritons emerging from the target are trapped in stacks of foils situated around the target, and after an exposure tritium
content is measured in each foil. The use of this technique has made it possible to investigate the fundamental
features of nuclear reactions involving triton formation.
Geophysical Research
Tritium is being widely employed in current geophysical research. Since the half-life of tritium is negligibly
small compared to geological time, some constant source of tritium on the earth is required for its continued presence.
Until 1954, the primary source for the formation of tritium on the earth was constituted by cosmic rays. During the
past 7 years, the amount of tritium has increased some 10-15 times, which is due to tests of thermonuclear weapons.
Tritium content in atmospheric precipitation, in air samples, and in surface waters is now decisively dependent on
the place, time, and nature of the explosions carried out. This has been very convincingly demonstrated by W. Libby
( USA) in a long report read to the symposium. Tritium content in precipitates and water samples is observed to be
a linear function of the amount of thermonuclear material exploded.
The thermonuclear origin of atmospheric tritium is strikingly confirmed by the clearly defined correlation be-
tween tritium content and Sr content in precipitates and fallout. Measurements carried out during the years 1958-
1960 show that the content of both isotopes in fallout varies with time in an identical manner. In the spring of 1959
a sharp maximum in the content of both isotopes was observed; this is related, in Libby's view, to tests performed
during the autumn of 1958. Since the summer of 1959, following the cessation of nuclear weapons testing, tritium
and Sr" content in atmospheric precipitation has fallen off sharply.
On the papers devoted to tritium formation in nature unrelated to thermonuclear explosions, one worthy of
particular attention, presented by E. Feierman (USA), reported a variation in tritium content in meteorites and in the
outer casings of artificial satellites brought back from circumterrestrial orbits. The quantity of tritium measured in
meteorites (seven stony meteorites and eight iron meteorites were studied) agrees in general terms with what one
would predict from the effect of primary cosmic particles. However, the tritium content found in the material of
satellites turned out to be many times higher than that formed in response to bombardment by cosmic rays. The
satellite Discoverer-XVII was launched on November 12, 1960 and was in orbit for 50 hours with apogee at 995 km
and perigee at 185 km. An intense solar flare appeared on the sun several hours prior to the launching. Tritium con-
tent in the satellite material proved to be several thousand times higher than in meteorites. Tritium content in the
material of the Discoverer-XVIII satellite, launched on December 7, 1960 into an orbit with similar orbit parameters,
proved to 10-20 times less than in the preceding satellite, but still many times larger than in meteorites. One
plausible explanation to account for the results obtained is that tritium was formed as a result of nuclear reactions on
the surface of the sun during the period of increased solar activity. Some of this tritium reached the earth and was
trapped in its vicinity for some time following the flare. Pursuance of these investigations should be of great interest
in the study of solar processes.
The hydrological investigations reported on at the symposium refer predominantly to the study of ground water
flow in different localities and terrains. The study was carried out by concurrent measurement of natural tritium
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and introduction of tritium into water reservoirs, in some cases. Experimentation showed that the use of tritium in
this type of investigation yielded results in no wise inferior, with respect to precision and accuracy, to those attained
by other methods. Investigations in the area of oceanology pertain primarily to the study of the mixing rate of waters.
Isotope Effe cts of Tritium
Great differences in the masses and zero energies of hydrogen isotopes lead to very noticeable isotope effects
in the case of tritium which cannot be ignored when evaluating the results of experiments involving isotope exchange.
The more generalized theoretical problems involved in isotope effects were considered by Ya. M. V arshavskii (USSR)
and Y. Biegeleisen (USA).
Varshavskii's paper described a method of statistical-thermodynamical calculation of equilibrium isotope effects
for various types of hydrogen isotope exchange reactions. Calculated values of tritium distribution coefficients (a)
for protium-tritium exchange between different components at 20?C were presented. It was shown that the value of
a may reach very high values (above 20) for some systems (e.g., hydride of an alkali metal ? hydrocarbon system).
The physical fundamentals of the general approach which had made it possible to predict the values of a for isotope
exchange in any systems of hydrogen-containg substances were formulated in this paper.
The problem of the relationship between isotope effects for deuterium and tritium was considered in Biegeleisen's
paper. The predominant role is attributed to what is known as the primary isotope effect, corresponding to processes
accompanying the scission of chemical bonds or major effects due to bond disruption. The secondary effect, much
smaller in scope, is due to a change in intermolecular forces. A method for tentative calculation of tritium isotope
effects based on data dealing with deuterium isotope effects was laid bare in this paper.
Methods for Introducing Tritium into Molecules
The very simple and convenient method for introducing tritium into molecules of complex organic compounds
suggested by K. Wilzbach in 1957 has opened up broad perspectives for the use of tritium as a tracer atom in organic
chemistry, biochemistry, and biology. The gist of the Wilzbach method is that the substance to be investigated is
placed in an atmosphere of gaseous tritium, the isotope exchange process sets in and protium atoms are replaced by
tritium atoms. One essential feature is that in the case of tritium exposure, in contrast to deuterium labeling, ex-
change takes place not only at the O-H- and N-H-bonds, but also at the C-H- linages. The Wilzbach method has
been extended at present to promote tritiation of gaseous, liquid, and even solid compounds. The mechanism of the
corresponding isotope exchange reactions is still somewhat obscure, but available data support the view that hydrogen
exchange is a radiation-chemical process initiated by tritium-emitted betas.
In his report to the symposium, K. Wilzbach (USA) presented new data on the method which he discovered and
which bears his name. The paper laid special emphasis on radiation-chemical side reactions taking place in the
system. One typical trait of the method is the nonuniform distribution of tracer throughout the molecule. For ex-
ample, in the case of toluene, the content of tritium in the ortho position is 16 times the tritium content in the CH3?
group, while the tritium content at the meta?and para- positions is 7 times as great as in the Cl-I3? group. And in
the mandelic acid molecule, tritium concentration in the aromatic ring is 750/0 of tritium content in the CH(OH)COOH
functional group.
Other techniques for tritium-labeling of molecules were also discussed at the symposium, (e.g., exchange in an
electrical discharge, exposure to ultraviolet light, etc.). As a rule, the different techniques are distinguished mainly
by a preferential labeling of different sites in a molecule. For example, the Wilzbach labeling technique leads to
a preparation labeled predominantly in the ring in the case of toluene, whereas toluene labeling under an electric
discharge chiefly affects the CH3? group (H. Ache, West Germany).
Problems involving preferential tritium labeling of iodine-containing compounds were dealt with in a paper by
P. Feng (USA). Interacting with tritium gas, iodine is easily replaced by tritium with the formation of selectively
tagged compounds.
Labeling of complex organic compounds without the use of tritium gas was the topic treated by two reports.
D. Garnett (Australia) told of experimental findings on isotope exchange between T20 and aromatic hydrocarbons
and their derivatives in the presence of platinum catalyst. A typical feature of the isotope exchange reaction with
T20 was the pronounced difference in rate of exchange for various hydrogen atoms on the aromatic ring. The
catalytic exchange method has some advantages over the Wilzbach method, since more selectively tagged products
can be arrived at through the former method. R. Falter (USA) devoted his paper to isotope exchange between vapors
of organic substances and heated uranium tritide.
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Several reports touched on the biosynthesis of tritium-labeled biologically active compounds.
Investigations of Mechanisms in Chemical Reactions
D. Barre (USA), in a review paper, took up questions associated with the use of tritium in the radiation chem-
istry of organic compounds. The origin of hydrogen atoms liberated in radiolysis can be determined in some cases
by introduction of tritium as tracer atom, as can the mechanism of interaction between hydrogen gas and organic
matter, etc. The data obtained were correlated with data available for deuterium. This comparison resulted in a
successful evaluation of the dependence of isotope effects on the mechanism behind the process, and in drawing of
inferences on the effect of the intrinsic radiation of tritium on radiolytic and isotope exchange processes in the sys-
tems studied.
A. Powell (USA) told of results of an investigation of the Cannizzaro reaction using tritium tracer in the para-
positions of benzaldehyde and phenyl benzoate. The principal inference drawn from the research is that the first
stage of the Cannizzaro reaction is an intermolecular shift of the hydride ion, rather than an intermolecular displace-
ment of hydrogen. The isotope effect discovered for this reaction is an indication that the stage of proton transfer
follows the first stage, rather than running concurrently with the shift of the hydride ion.
D. Beal (Britain) reported on applications for a highly promising double-labeling (I-13 and C14) technique. This
method makes it possible to study the amino acid composition of proteins in trace quantities (of the order of micro-
grams), opening up new opportunities in protein chemistry.
Biological Investigations
Roughly half of all the papers submitted to the symposium dealt with tritium applications in biological research.
These may be subdivided under two headings: 1) papers in which radiation effects of tritium on biological systems
are investigated; 2) papers dealing with the study of various biological processes with tritium used as tracer atom.
The radiation effects of tritium may have the effect of accelerating hydrogen isotope exchange, with some loss
of tracer as a result, and may lead in some instances to appreciable changes in the characteristics of the biological
system. Results of a study of tritium beta effects on the growth and activity of ricketsial bodies, influenza virus,
intestinal bacilli, the bacterial flora of the cud of large horned cattle, etc. were presented in some papers. A paper
by E. Cronkite (USA) dealt with a study of the toxicity of tritiated thymine.
The possibility of employing the beta radiation of tritiated drugs to cure cancer was examined in a paper by
D. Marian (Britain). A high-activity (28 curies/mole) preparation was synthesized, and this preparation readily
gained access into living cells. The intake of malignant cells was found to be more rapid than that of healthy cells.
It is important that assimilation of the preparation by bone marrow cells proceed at a rate of at most only one fifth that
of tumor cells. Positive results were indicated from use of this preparation on patients.
Papers devoted to the use of tritium tracer touched on research into the broadest variety of biochemical processes:
most of the reports dealt with particular problems. At the same time, several methodological novelties of some in-
terest were reported on. A paper by J. Hampton (USA) demonstrated new opportunities for the simultaneous use of
autoradiography and electron microscopy for the study of cell processes in vivo. The method suggested was success-
fully employed for detailed monitoring of the process of incorporation of tritiated thymine into the nucleus of a DNA
cell.
W. Sin i (USA) presented his findings from an investigation of isotope exchange in animal organisms. The analysis
showed that approximately 981 of the tritium introduced into the organism was incorporated into the body water, and
2% into the tissues.
Many papers were devoted to a study of cell metabolisms using tritiated thymine and cytidine preparations. In
particular metabolic studies were made of bone marrow cells (F. Gavosto, Italy; W. Bond, USA), tissue metabolism of
thyroid hormones (J. Roche, France), etc.
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SEMINAR ON THE USE OF ISOTOPES AND NUCLEAR RADIATIONS
IN BLAST FURNACE PRODUCTION
P. L. Gruzin
Translated fromAtomnaya gnergiya, Vol. 11, No. 3,
pp. 268-269. September, 1961
A broad research and development plan for applications of radioactive isotopes and nuclear reactions in the
metallurgical industry was started in the USSR in 1948-1949. At the present time, many research projects on the
possible applications of isotopes and nuclear radiations are being completed at factories and inInstitutes. This has
pointed up a need for topical seminars on special problems in metallurgical production.
A seminar on the use of isotopes and nuclear radiations in blast furnace production was held during March 1961
at Dneprodzerzhinsk, under the sponsorship of the Commission of the State Scientific and Engineering Committee
of the Russian Soviet Federated Socialist Republic on the integration of isotopes and nuclear radiations into industry,
and of the Dzershinskii metallurgical plant. Over 50 scientists and engineers engaged in the development and pro-
duction engineering of various isotope and radiometric techniques and instruments in blast furnace production took
part in the seminar. The most important metallurgical enterprises of the nation (the Dzerzhinskii plants, the Il'ich
"Azovstal' " plant, the Stalino (Donets), Krivoi Rog, Novaya Tula, Cherepovets, KMK, YuGOK, etc, plants) were
represented at the seminar, along with leading scientific and research Institutes engaged in metallurgical studies
(TsNIIChM ferrous metallurgy research institute, the Ukrainian Institute of Metals, the Dneprodzerzhinsk metallur-
gical institute, the Moscow Engineering and Physics Institute (MIFI), and other). 19 papers and communications on
the use of radiation and isotope methods and instrumentation for monitoring, control, and investigation of blast furnace
production processes were read to the seminar. The participants benefited from trips to the Dzerzhinskii plant, the
Krivoi Rog metallurgical enterprise, and the YuGOK enterprise, where they became acquainted directly at shop level
with the substance of the advances based on isotopes and nuclear radiations, and with the process instrumentation of
these major plants. All of this was an enormous aid to the seminar participants in carrying out a detailed discussion
of the contents of the papers, and singling out the perspectives of further work.
Let us spend some brief time on typical reports made to the seminar, and outstanding remarks by participants.
? P. L. Gruzin (Moscow) and A. D. Kutsenko (Dneprodzerzhinsk) gave, in their papers, a general evaluation of the
status of work on applications of instruments and nuclear radiations in various branches of metallurgical production,
and shed light on the perspectives of further production-line exploitation of the achievements of nuclear physics in
metallurgical practice. Attention was drawn to the extensive opportunities for the use of radiation sensors whose
functioning is based on the use of 8- and y - and neutron radiation, and various process control systems of metallur-
gical interest. The applications of neutron sources of radiation for continuous monitoring of high temperatures and
moisture of raw materials was discussed in particular. Possibilities for the use of radiometric techniques to monitor
the dimensions of hot-rolled product of complex configuration were discussed, as well as the activation analysis
method in application to blast-furnace burden, and the method of gamma-neutron probing of the tuyere zone and the
shaft of the blast furnace. In the discussions on the papers, it came out that all of these questions are of vital sig-
nificance to the plans for starting up the world's largest blast furnaces in our country.
A report by I. G. Polovchenko and V. N. Uzlyuk was devoted to a review of research involving tracer and
radioisotope studies carried out at the Dzerzhinsk plant in cooperation with the TsNIIChM institute. The reporters
limited their treatment in the main to a generalization of data from their own investigations, partially known to
the participants of the seminar from published materials. Data on the economic effectiveness of the use of various
radiometric techniques and instruments in blast furnace process control were heard with intense interest. It was
pointed out in their report that isotopes have been successfully employed to extract valuable data on problems in-
volving control of the blast furnace melting furnace, for improving furnace design, atutomation and correction of
operations during a heat, with a resulting increase of 2.5-31 in pig iron melts, a 3-3.50/0 reduction in fuel costs,
and a 5-8010 increase in furnace operating life.
Several reports and statements from the floor were devoted to peculiarities in the design of on-off and servoed
radiometric level gages for monitoring the level of blast furnace burden, and the results of industrial production tests
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at the Dzerzhinskii plant. All of the reporters and commenters introduced many valuable suggestions on improving
individual components in the existing prototypes. V. I. Afanas'ev and V. G. Smirnov gave a brief characterization
of the design of a new model of servoed radiometric burden level gage (URMS-2), developed by TsNIIChM on the
basis of industrial tests of the device under production conditions at the Dzerzhinskii plant. The participants at the
seminar acknowledged the feasibility and timeliness of the installation of UFtMS-2 devices at 15 blast furnaces of
the NTMZ, Krivoi Rog, KMK, Il'ich, and other metallurgical plants during the 1961-1962 period.
Several reports and comments were devoted to a discussion of radiometric techniques for control of hot spots
in the well of blast furnaces (at the Dzerzhinskii, KMK, "Azovstal' ", Il'ich, and NTMZ plants). These techniques
have been in use at over 30 furnaces. The method was first tried out in 1950 at the NTMZ plant, and data extracted
from the experiment provided a basis for suggestions toward enhancing well durability (increased cooling facilities,
use of improved refractories, etc.). Subsequent research work at those plants confirmed the correctness of those
suggestions, which have been incorporated in good measure into blast furnace construction practice, with excellent
economic returns of a qualitative nature. The method developed for checking hot spots in the blast furnace well
has been adopted by other countries.
A. V. Pugachev (Tula) devoted his paper to a discussion of results of industrial testing of a radiometric facility
designed to monitor the degree of sintering of sinter cake. V. M. Ivanov pointed out several difficulties standing in
the way of adapting this device to production conditions at KMK. N. S. Gogin (NTMZ) noted that the use of the
radiometric method for monitoring the degree of sintering of sinter cake under high-temperature operating conditions
is of enormous significance.
The seminar also took up the results of a study of the rate of flow of burden materials in blast furnaces (of the
Dzerzhinsk "Avozstal' " plants), the perspectives for the use of radiometric methods in quality control of burden
(TsNIIChM), and some questions relating to blast furnace production theory where isotope applications are concerned
(Dneprodzerzhinsk metallurgical institute). A paper presented by A. S. Golovan' dealt with the perspectives for the
development of research on radioisotope applications in enterprises of the Dnepropetrovsk Council of the National
Economy.
At the concluding session of the seminar, a resolution was adopted in which the most efficient approaches for
implementation of isotope and nuclear radiation techniques in blast furnace production were indicated. The par-
ticipants of the seminar pointed up the need for a systematic program of topical seminars on applications of radio-
active isotopes and nuclear radiations in particular branches of metallurgical industry. We may accordingly rest
assured that this first experience in carrying out topical seminars of this nature has been a positive one.
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ISOLATION OF TECHNETIUM
A sophisticated process [1] for obtaining kilogram quantities of technetium Te99 (weak beta-emitter with a
half-life of 2.12.105 yrs) from spent nuclear fuel has been developed at ORNL. To date, most of the technetium was
extracted, along with uranium in UF6 obtained by fluorination of uranium trioxide, from spent uranium. Anion ex-
change techniques have been successfully employed to extract technetium more efficiently. The technetium from
a concentrate containing negligible amounts of fission fragments and ions of aluminum, calcium, sodium, uranium,
and fluorine, was extracted with 2,4-dimethylpyridine. The organic phase was distilled off and Tc99 was collected
in the residue with some amounts of impurities from the concentrate and with the dimethylpyridine. This product
was extracted to remove organic impurities, using an extractant mixture of tri-n-octylamine in benzene. Pure
technetium was isolated in the form of ammonium pertechnate by repeated crystallizations from a solution of
ammonium nitrate. This salt was reduced by contacting with hydrogen at 400-500?C, and a metallic powder con-
taining over 99.9% Tc99 was obtained. This improvement in technology brought the cost of technetium down from
1600-2800 dollars/gram to 100 dollars/gram. At the present time, the monthly output at a pilot plant has increased
a thousandfold and amounts to about 400 g of metal, but may be increased further to meet mounting demands. The
pertechnate ion?a powerful inhibitor of corrosive attack by water on iron and steel ? is being eyed as a potential
anticorrosion medium for boiling water reactors. Tc99 has the added distinction of being an excellent superconductor
(the transition temperature of 11.2?K is the lowest [2] for the elements). Its melting point is ?2200?C [3]. Most of the
fundamental properties of this element have yet to be studied, although some considerations on its possible alloys are
discussed in the literature[4].
LIT ERA TURE CITED
1. Chem. Engng. News, 39, No. 9, 52 (1961),
2. A. N. Murin et al. Uspekhi khimii. 30, 249 (1961).
3. E. Anderson et al. Nature, No. 1883, 48 (1960).
4. N. V. Ageev et al. Doklady akad. nauk SSSR, 129, 555 (1959).
REFLECTING BETA THICKNESS GAGE MONITORS SETTLED
COAL DUST IN MINES (ROTOP-3A GAGE)
The use of the principle of the reflecting thickness gage [1] has aided in the development of a device for
sensing the amount of dust precipitated on the surfaces of mine workings, an advance of no mean significance for
miners' safety conditions.
The radiation -actuated reflecting thickness gage for monitoring coal dust, the ROTOP-3 [2,3], developed by
the State Makeev Scientific Research Institute of Work Safety in the Mining Industy jointly with the Khar'kov Mine
Surveying Instruments Manufacturing Plant (KhZMI), has passed industrial tests with flying colors and has been
recommended for routine use.
In 1960, KhZMI engineered industrial production of a modernized version of the ROTOP-3A thickness gage.
The functioning of this instrument is based on changes in the intensity of reflected beta radiation by the isotope
T1204 as a function of the thickness of a layer of monitored coal dust lying on tope of a rock substrate. The presence
of an appreciable difference in atomic numbers (of the order of 7-8 units) between the coal, which is the exposed
material in the given case, and the host rock which is the bulk material forming the substrate, provides the necessary
conditions for successful functioning of the radiation thickness gage.
The gage (Fig. 1,2) consists of a planar ionization chamber with a stretched aluminum foil and polyethylene
film covering the entrance window a compartment for an annular radiation source surrounding the ion chamber, a
d-c electrical amplifier, and a microammeter calibrated in units of surface concentration of dust.
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Fig. 1. General view of the ROT OP-3A
930
The annular emitter is made up of 29 point sources
of T1204 built up on the base of a standard B1 source. The
total activity over the emitter surface is 5 microcuries.
The d-c amplifier is based on a 2E2P electrometer tube
included in a balanced bridge circuit. The electrical com-
pensation of the initial current provided for in the circuit
makes it possible to amplify and measure only that part of
the ionization current which is due to reflection from a
coal-dust layer.
The redesigning of the instrument for transient
measurements under the natural conditions prevailing in
coal pits, with a rather uneven and rough contouring of the
rock substrate, necessitated considerable changes from the
more familiar coating- layer thickness gages, and added to
the difficulties hampering measurements. The principal
difficulty is due to the impossibility of constantly com-
pensating initial current, since the contouring of the surface
to be monitored is different for any run of measurements.
Fig. 2. Cross-sectional view of the ROTOP-3A thickness gage; 1) shielding
screen; 2,4) supply compartments; 3) micorammeter; 5) electrometer tube;
6) ion chamber housing; 7) amber insulator; 8) grid electrode; 9) radiation
source; 10) diaphragm for entrance window.
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The redesigning of the instrument for transient measurements under the natural conditions prevailing in coal
pits, with a rather uneven and rough contouring of the rock substrate, necessitated considerable changes from the more
familiar coating-layer thickness gages, and added to the difficulties hampering measurements. The principal diffi-
culty is due to the impossibility of constantly compensating initial current, since the contouring of the surface to be
monitored is different for any run of measurements.
A procedure of measurements was developed to eliminate any effects of mine topography on the results, and
functions as follows. The gage is placed on a rock substrate covered with coal dust. All of the current due to re-
flection of radiation is compensated by feeding in compensating voltage, and the gage is reset to zero. A rubber
bulb is then squeezed to blow away an area of dust from underneath the instrument, and the compensation voltage
proves insufficient in view of the increased reflection. The circuit then balances out at a level proportional to the
amount of dust removed, and this is recorded by the output device. When compensating voltage is used in this
manner, some constant contribution from the voltage is always placed across the control grid of the measuring part
of a 2E2P double tetrode to drive the grid bias to a value equal to the bias voltage across a second control grid, i.e.,
actually to reset the amplifier. The remaining portion of the voltage, whose function is to directly compensate
ionization current, varies in different measurements and is higher or lower depending on the surface topography of
the section of mine being monitored. The effect of surface topography on instrument readings is thereby virtually
eliminated, enhancing the use of the gage as a portable instrument.
The measurement range of the instrument runs from 0 to 70 g/m2 with a sensitivity of 1 g/m2. Within these
limits, the thickness of a coal-dust coating is far removed from what is known as infinite thickness, so that the in-
strument scale is linear. For the same reason, any unevenness in dust distribution is without effect on instrument
readings within an effective surface area range of ?150 cm2. The error in the measurements does not exceed 10 %
of measured value over the range 10-70 g/m2. The instrument weighs 3.2 kg. Mercuric oxide batteries and wafer
cells are used as power supplies. The instrument is operated by a single operator. The leaktightness of the radiation
sources and the comparatively high hardness of the radiation from the isotope selected for the job (Emax = 0.765 Mev),
as well as the presence of shielding "jaw" hinges shutting off the emitter when in "off" position, fully guarantee
radiation safety of the instrument in conformity with the latest public health rules.
Experience in the use of the gage has demonstrated the efficiency of ROTOP-3A gages in rendering serious
assistance while safeguarding mine safety conditions for the benefit of miners.
LITERATURE CITED
1. E. Clarke, S. Carlin, W. Barbour. Electr. Engng., 70, No. 1, 35 (1951).
2. F. E. Krigman et al. Patent No. 113576, 1958.
3. Ya. N. Fortel'meister et al. Ugol', No. 1, 48 (1959).
All abbreviations of periodicals in the above bibliography are letter-by-letter transliter-
ations of the abbreviations as given in the original Russian journal. Some or all of this peri-
odical literature may well be available in English translation. A complete list of the cover- to.
cover English translations appears at the back of this Issue.
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Brief Communications
Poland. In line with the decision adopted by the X session of the Learned Council of the Joint Institute for
Nuclear Research, a conference on cyclotron-based scientific research was held June 5 to 10, 1961, at the Institute
of Nuclear Physics at Krakow. Reports from physics institutes of member nations of the Joint Institute for Nuclear
Research were presented to the conference. The agenda of the conference included an exchange of experiences on
the performance and further improvement of the U-120 model cyclotron, specimens of which are being used in many
institutes of member nations of the Joint Institute, and time was set aside for a discussion of the results of physics
experiments carried out on accelerators, and trends in future research.
Participants learned from the papers presented that a stable mode of acceleration had been achieved by the
time of the conference on all U-120 cyclotrons in use, and that experimental researches are being undertaken on a
broad scale. Possibilities for expanding the range of accelerated particles, increasing the limiting energy, and
monochromatizing beams of accelerated ions were also discussed.
It should be noted that despite individual technological flaws which came to light in the process of testing and
adjustment, the U-120-1 cyclotrons developed and fabricated by the Institute of Electrophysical Equipment (USSR)
have come in for high praise at the conference.
A wealth of experimental material dealing with scattering on the nuclei of various particles has been amassed
in recent years. Papers were read to the conference on measurements of spectra and angular distributions of neutrons
and charged particles in reactions of types (d,n); (d,t); (a,n); (a,t), etc. The discussion demonstrated the need for
further research efforts in these areas, and the urgency of obtaining intense beams of polarized protons on the cyclotron.
In experiments on investigation of gamma radiation appearing in response to bombardment of some nuclei by
protons, deuterons, and heavy ions, a certain amount of interest has centered on the study of cascade gamma transi-
tions in (a, y) reactions, and on experiments probing into coulombic excitation of levels in nuclei.
Much attention focused on problems of technique, particularly semiconductor detectors for charged particles.
The silicon detectors developed and manufactured at the Nuclear Research Institute (of Czechoslovakia) have
excellent linearity into the 12 Mev proton energy range, and an energy resolution not inferior to 0.6%. Laboratories
equipped with these silicon detectors could simplify their experimental methods appreciably, and effect an increase
in the accuracy of their measurements.
The last session also discussed the problem of improving avenues of scientific information exchange between
the institutes of the various member-nations of the Joint Institute.
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BIBLIOGRAPHY
NEW LITERATURE
Books and Symposia
Translated from Atomnaya Energiya, Vol. 11, No. 3,
pp. 287-294, September, 1961
J. Bowen, E. Neisters. Upravlenie yadernymi reaktorami: a translation of Nuclear Reactor Control published
in Britain. Moscow, Gosatomizdat, 1961. 96 pages, 30 kopeks.
The book reviews the basic parameters of the control system of gas-cooled uranium-graphite reactors. The
effect of changes in reactivity and speed of coolant flow on reactor performance in different operating modes is
described, and a method for studying transients by analog simulation is presented. Specifications for control components
and loops are given.
The concluding chapter contains a concise description of instruments for measuring neutron flux.
The book is written for scientific and engineering personnel and technicians engaged in the design and operation
of nuclear reactors, and for students majoring in nuclear engineering.
P. Margen. Vybor optimal'nykh variantov v reaktorostroenii Abridged translation from the English. [Optimiza-
tion of reactor design] Moscow, Gosatomizdat, 1961. 100 pages, 40 kopeks.
This book is devoted to the timely question of the economics of nuclear electric power generating stations, to
the optimization of power station parameters on the basis of an engineering economics analysis. The objects of
analysis in this book are the reactor core, heat transfer and friction, and the thermodynamic cycle, which are
approached in the context of a power station built around a gas-cooled reactor using heavy water moderator. The
book contains six chapters. The first chapter outlines in popular style the procedure for the engineering costs analysis
of the conductor carrying the current. Subsequent chapters provide the fundamental relationships for physical and
thermal core calculations and for calculating the thermodynamic cycle of the station.
A procedure is considered for optimizing core parameters and heat transfer parameters in a physical analysis,
and some considerations on the proper choice of thermodynamic cycle for a nuclear power station are outlined in
brief.
The appendices present formulae and tables needed for calculating optimum parameters for a nuclear power
station.
The book is written for nuclear power specialists engaged both in reactor core calculations and in the design
of power engineering equipment, and for graduate students specializing in nuclear power engineering.
V. L. Shashkin. Metody analiza estestvennykh radioaktivnykh elementov. Moscow, Gosatomizdat, 1961. 152
pages, 47 kopeks. [Methods of analysis of natural radioelements].
This book provides a review of radiometric and nucleonic methods in the analysis of elements in the uranium,
radium, and actinium-uranium series in natural formations and in products of uraniferous and thoriferous ore processing.
Characteristics of the radioactive properties of natural radioactive elements are given. Methods for the measurement
of radioactive radiations are described, and techniques of analysis based solely on measurements of radioactive
radiations are outlined.
Methods for determination of uraniurn, thorium, protactinium, actinium, and polonium are presented, in addi-
tion to the emanation methods of such vital importance in the determination of radium and radon isotopes. The
principles of complex radiochemical analysis are elucidated. The list of useful literature references appended in-
cludes 126 titles.
The book is written for radiochemists and physicists working in the field of analysis of natural radioactive elements.
It may also prove useful to students majoring in those topics.
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I. NUCLEAR POWER PHYSICS
NEUTRON AND REACTOR PHYSICS. PHYSICS OF HOT PLASMAS
AND CONTROLLED FUSION. PHYSICS OF ACCELERATION OF CHARGE
PARTICLES
Doklady akad. nauk SSSR, 137, No. 4 (1961)
B. N. Gershman 822-25. On some features of transverse propagatioh of microwaves in a magnetoactive plasma.
Zhur. tekhn. fiz., XXXI, No. 6 (1961)
Ya. B. Fainberg et al., 633-39. Note on the nature of instabilities in interactions between charged-particle
beams and a plasma.
V. S. Imshennik, Yu. I. Morozov, 640-49. Analysis of instability of a beam of charged particles in an electron
plasma.
M. D. Gabovich, I. M. Mitropan, 6-16-79. Observation of hydromagnetic oscillations in the plasma of a pulsed
electrodeless discharge.
Zhur. eksptl. i. teoret. 40, No. 5(1961)
A. I. Morozov, L. Solov'ev, 1316-24. Kinetic examination of some plasma equilibrium configurations.
P. S. Zyryanov, 1358-56. Quantum theory of acoustic oscillations of an electron-ion plasma in a magnetic
field.
Yu. N. Dnestrovskii, D. P. Kostomarov, 1404-10. On the dispersion equation for an ordinary wave propagating
in a plasma at right angles to the externally applied magnetic field.
M. T. Zhumartbaer, 1434-39. On the stability of magnetic tangential discontinuities in relativistic hydro-
dynamics.
Izvestiya akad. nauk SSSR, seriya fiz., 25, No. 4 (1961)
A. K. Trofimov, 460-61 Luminescence of lanthanides in thorium oxide.
B. S. Grebenskii et al., 500-503. On enhancing the efficiency of slow-neutron scintillation detectors.
G. V. Gorshkov et al., 504-505. A disperse-phase-fast-neutron detector.
Pribory i tekhnika elcsp., No. 2 (1961)
S. Ya. Nikitin, 5-13. Modem techniques in processing bubble chamber plates.
Yu. M. Khirnyi, L. N. Kochemasov, 14-19. Injector for negative hydrogen ions.
0. D. Kovrigin et al., 19-25. A double-focusing large beta-ray spectrometer.
V. N. Lukashev, 26-34. Analysis of electron trajectories in an axial beta-ray spectrometer with centrally
placed source.
V. F. Litvin, 33-34. Double focusing over a broad energy range with the aid of sectored homogeneous magnetic
? fields.
A. I. Veretennikov et al., 42-46. Gamma-ray spectrometer uses organic scintillator with time sampling of
gamma radiation.
M. I. Daion et al., 47-52. Spark-counter telescope in a magnetic field measures pulses of fast charged particles.
A. M. Ratner, I. A. Rom-Krichevskaya, 53-62. Note on the theory of energy resolution in scintillation counters.
A. E. Voronkov et al., 63-68. New instrument automatically scans nuclear emulsions by the TV raster method.
I. Servo system.
E. Fenyes et al., 68-72. Semiautomatic measuring instrument for processing bubble chamber plates and Wilson
chamber plates.
V. I. Strizhak, N. S. Nazarov, 72-75. Neutron generators.
V. N. Bochkarev, V. V. Nefedov, 80-81. Scintillation detector for separately recording heavy and light ionized
particles.
N. A. Vitbvskii et al., 82-83. Silicon n-p-counters for heavy charged particles operate without supply sources.
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Amer. J. Phys., 29, No. 4 (1961)
J. Solbrig, 257-61. Doppler effect in neutron resonance absorption.
Amer. J. Phys., 29, No. 5 (1961)
C. Ananiades, J. Dewdney, 329. Alpha-particle semiconductor detector.
Energia Nucleare, 8, No. 4 (1961)
C. Galotto et al., 243-46. Design of photoneutron source and its calibration.
Nucl. Energy, No. 156 (1961)
- -, 199-200. Methods and equipment for training courses in nuclear physics.
Nucl. Instrum. and Methods, 10, No. 4 (1961)
D. Caro, J. Rouse, 249-58. The variable-energy cyclotron at Melbourne University.
G. Wilson, 259-62. Phase variations near the center of a cyclotron.
G. Kelley et al., 163-71. Source of high constant ion currents.
I. Myers, H. Larson, 281-88. Precision instruments for monitoring beams in electron accelerators.
R. Glover et al., 343-47. Telescopic counter system for fast-neutron experiments.
H. Grassier, K. Tesch, 353-55. Detection efficiency of a plastic scintillator for neutrons in the 1-14 Mev
energy range.
Nuovo Cimento, XIX, No. 6 (1961)
H. Carvalho et al., 1131-41. Angular distribution of uranium photofission fragments.
Techn, Digest, III, No. 6 (1961)
- -, 48-50. Microscope for measuring nuclear particle tracks.
II. NUCLEAR POWER ENGINEERING
NUCLEAR REACTOR THEORY AND CALCULATIONS. REACTOR DESIGN.
PERFORMANCE OF NUCLEAR REACTORS AND POWER STATIONS
Atompraxis, 7, No.4 (1961)
H. Bildstein, P. Koss, 126-28. The ASTRA reactor fuel elements.
W. Cawley, 131-35. Problems in load transfer of fuel elements.
H. Benzler, 135-41. Power engineering problems in a gas-cooled reactor.
H. Schudi, 142-46. Approximate calculation of optimal pitch in uranium lattices.
Atompraxis, 7, No. 5 (1961)
J. Stohr, 189-93. Fuel elements for graphite-moderated reactors using pressurized-0O2 coolant.
Energia Nucleare, 8, No. 4 (1961)
G. Zorzoli, 255-60. Theoretical investigations and experimental results obtained for critical assemblies with
moderator of organic fluid and water.
F. Castelli, 161-69. The Enrico Fermi nuclear power station.
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I. Bachmann, 270-75. Experience of the first stages of operation of the Yankee Atomic reactor.
M. Covino, R. Lepore, 176-87. Details of the planning and development of the Garigliano nuclear power station.
Ji.dern-a Energie, 7, No. 5 (1961)
- -, 158-66. Physics of heavy-water reactor lattices.
Kernenergie, 4, No. 4 (1961)
W. Fratzscher, R. Nitsch, 269-75. Evaluation of heterogeneous reactors from the standpoint of thermodynamic
potential.
A. Sydow, 276-84. The UNIMAR analog computer in nucleonics programs.
Kernenergie, 4, No. 5 (1961)
H. Hessel, 384-90. Note on the problem of constant burnup in pressurized-water reactors.
Nucl. Energy, No. 156 (1961)
- -, 201 The NESTOR neutron source reactor
- -, 202-204. The Sizewell nuclear power station.
B. Link. Clark, 205-209. Model of an experimental reactor for studying heat transfer.
- -, 209. Reloading mechanism of the AGR reactor.
Ncul. Engn., 6 No. 61 (1961)
- - , 239-52. Maritime heavy water reactor with steam cooling system.
Nucl. Power, 6, No. 62 (1961)
J. Collier, 61-66. Fuel burnup in liquid-cooled reactors. 1.
- -, 70. Thermocuples for elevated temperatures.
S. Hollands, 78-79. The export policy of the USA in the nuclear power field.
Nucl. Sci. and Engng., 9, No. 4 (1961)
C. Orth, 417-20. Diffusion of lanthanides and actinides from graphite at high temperatures.
G. Smith et al., 421-29. Experimental investigation of resonance capture of neutrons by U238 in UO2 fuel
elements.
D. Parks, 430-41. Effect of motion of atoms on thermalization of neutrons.
G. Boyd, et al., 442-54. Flow transients in a multiloop reactor system.
E. Hellstrand, J. Weitman, 507-18. The resonance integral for thorium in the form of metallic rods.
Nucleonics, 19, No. 6 (1961)
D. Keller, 45-48. Calculating fuel burnup for stainless-clad UO2.
F. Boni, P. Otten, 58-61. Steam generators for the Enrico Fermi power station and the Hallam nuclear power
station.
A. DeStordeur, '74 ff. Drag coefficients for remote-controlled components between fuel elements.
Nucleonik, 3, No. 2 (1961)
P. Weissglas, 54-57. Theoretical calculation of effect of lattice parameters on destruction of coolant channels
in a natural-uranium burner with heavy water moderator and coolant.
E. Kern, A. Schatz, 61-76. Diffusion of radioactive substances in solids of grainy structure.
W. Hage, L. Cameron, 76-80. Iterative solution of a system of kinetic reactor equations for a rod drop experi-
ment.
E. Eberth, W. Oldekop, 80-83. Two-group diffusion theory for a finite heterogeneous pebble-bed reactor.
P. Ahlstrom, P. Weissglas, 83-85. Spatial variations in concentration of isotopes in a fuel element rod.
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Reactor Sci. and Tech., 14, No. 1 (1961)
W. Blackburn, 1-8. Deflection of fuel elements in assembly due to creep.
M. Reier, J. De Juren, 18-24. Diffusion length of thermal neutrons in water over the 23-244?C temperature
range.
L. Blake, 31-48. Extensive fuel burnup in fast reactors.
R. Bertrand, 49-50. Determination of Pung content in a specimen of spent natural uranium, with the aid of an
alpha spectrometer.
D. Popplewell, 50-51. Specific a-activity and half-life of U233 .
J. Adam, M. Rogers, 51-52. Use of x-ray diffraction in the study of fission-fragment damage to uranium carbide
and uranium nitride.
III. NUCLEAR FUEL AND MATERIALS
NUCLEAR GEOLOGY AND PRIMARY ORE TECHNOLOGY. NUCLEAR METALLURGY
AND SECONDARY ORE TECHNOLOGY. CHEMISTRY OF NUCLEAR MATERIALS.
Doklady akad. nauk SSSR, 137, No. 3 (1961)
Yu. B. Pademo, G. V. Samsonov, 646-47. Electrical properties of hexaborides of alkali and rare-earth metals
and thorium.
Zhur. neorgan. khim., 6, No. 4 (1961)
0. L. Kabanova, 786-89. Complexing of plutonium (V) and EDTA.
I. I. Chernyaev et al., 790-98. On the complex nature of uranyl peroxide compounds.
A. V. Nikolaev, S. M. Shubina, 799-803. Nature of the linkage in complexes of uranyl nitrate and butyl-
phosphate compounds, from IR absorption spectra.
0. E. Zvyagintsev, L. G. Khromenkov, 874-82. On complexes between thorium and tartaric acid.
Chung Huang-Bang, P. I. Fedorov, 971-76. The ternary system thorium sulfate?sodium sulfate?water.
G. A. Polonnikova, L. V. Utkina, 1001-1003. On ammonium uranyl sesquicarbonate.
Zhur. fiz. khim., 35, No. 3 (1961)
L. M. Kovba et al., 563-68. Study of the crystalline structure of uranates. I. Uranates containing tetragonal
layers of (UO2)02.
D. A. Knyazev, 612-19. Calculating separation coefficients of isotopes in ion exchange.
Zavod. lab., 27, No. 5 (1961)
V. B. Spivakovskii et al., 390-91. Determination of traces of uranium in rocks and natural waters.
Radiokhimiya, 3, No. 2 (1961)
V. B. Shevchenko, V. S. Shmidt, 121-28. Extraction of ruthenium and several other fission products by tri-n-
octylamine from nitrate solutions.
V. B. Shevchenko et al., 129-36. Extraction of uranium (VI) and (IV) from chloride solutions by the diisoamyl
ether of methylphosphonic acid.
S. Mints, A. Ugnevskaya, 137-43. Effect of salting-out agents on extraction of uranyl nitrate by cyclohexane.
I. E. Stank et al., 151-54. Study of the state of protactinium in aqueous solution. IV. Ion exchange method.
V. I. Grebenshchikova, Yu. P. Davydov, 155-64. Study of the state of Pu(IV) in dilute solutions of nitric acid.
V. I. Grebenshchikova, Yu. P. Davydov, 165-72. Adsorption of Pu(IV) on a glass surface.
V. M. Vdovenko et al., 174-80. Vapor pressure above ether solutions of uranyl nitrate.
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P. N. Palei et al., 181-86. Express extraction-photometric determination of uranium using arsenazo III reagent.
V. M. Solntsev, Yu. M. Tolmachev, 187-94. Dissolution reaction of 1J808 in sulfuric acid. I. On the kinetics
of some reactions with powders.
J. Maly et al., 195-98. Reaction of plutonium dioxide with ammonium hydrogen fluoride in the absence of
water.
K. K. Aglintsev, 237-39. Determination of effective age of fission fragments.
V. F. Luk'yanov et al., 239-40. Analytic chemistry of thorium, III. Photometric determination of thorium
using arsenazo III in natural materials.
Fizika metallov i metallovedenie, 11, No. 3 (1961)
V. N. Strekalovskii et al., 400-403. Phase transformations in reduction and oxidation processes of uranium
oxides.
Atompraxis, 7, No. 4 (1961)
J. Robertson, 121-26. UO2 fuel elements.
B. Baines, 128-31. High-density graphite.
Canad. Mining and Metallurg. Bull., 53, No. 583 (1960) (1961)
W. Evans, 893-900. Metallurgy of highly reactive materials.
Kernenergie, 4, No. 5 (1961)
K. Helbig, 291-92. Determination of error in absolute activity measurements of specimens by the coincidence
method.
Kemenergie, 4, No. 5 (1961)
J. Fialkowski, R. Plejewski, 391-94. Spectrographic analysis of radioactive slurries.
Mining and Chem. Engn. Rev., 53, No. 6 (1961)
- -, 57-59, Processing of uranium ores.
Nucl. Energy, No. 156 (1961)
M. McQuillan, T. Farthing, 195-97. Beryllium.
0. Joklik, 211-20. Radiation polymerization of methylmethacrylate.
Nucl. Power, 6, No. 62 (1961)
G. Llewelyn, R. Allardice, 71-76. Experience in processing enriched fueld elements.
0. Plail, 81-82. Methods of irradiating fissile materials. 6.
Nucl. Sci. and Engng., 9, No. 4 (1961)
F. Sicilio et al., 455-61. Decontamination of irradiated tributyl phosphate by distillation in a kerosene-type
solvent.
J. Keyes, A. Krakoviak, 462-74. Niconel fatigue at 768? C due to high-frequency temperature oscillations.
G. Seaborg, 475-87. The transuranium elements.
T. Gens, 488-94. What's new in the processing of uranium-zirconium alloy fuel.
J. Williams, C. Huffine, 500-506. Electrolysis of yttrium metal in the solid state.
938
Nucleonics, 19, No. 6 (1961)
D. Worlton, 80-82. Ultrasonic testing of uranium slugs.
J. Bates, 83-85. Improving high-temperature thermal conductivity.
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IV. NUCLEAR RADIATION SHIELDING
RADIOBIOLOGY AND RADIATION HYGIENE. SHIELDING THEORY
AND TECHNIQUES. INSTRUMENTATION
Agrobiologiya, No. 2 (1961)
I. M. Vasil'ev, 259-69. Effect of ionizing radiations on plants.
Byul. Kirgiz. nauchno-issled. inst. zemledeliya, No. 5 (1960)
Ta. A. Ivanov, B. N. Kulikov, 43-46. Effect of irradiation of seeds by radioactive cobalt on the growth, de-
velopment, and crop yield of wheat and barley.
Zhur. Vsesoyuz. khim. ob-va im. Mendelleeva, 6, No. 2 (1961)
A. A. Kastal'skii, 193-99. Decontamination of sewage waters containing radioactive materials.
Izvestiya vyssn. ucheb. zaved. Lesnoi zhur., No. 1 (1961)
A. D. Tarabarin, 37-39. Uptake of P82 by mycorrhizic and nonmycorrhizic oaklets in relation to preliminary
phosphate treatment.
Izmerit. teldmika, No. 4 (1961)
M. R. Yudin, 0. A. Filippov, 37-42. Tissue-equivalent fast-neutron dosimeter.
V. S. Merkulov, 61-63. Soviet radioisotope-based instrumentation.
Pribory i tekhnika eksper.. No. 2 (1961)
M. Ya. Balats et al., 171. Fabrication of plastic scintillators by the press method.
Radiobiologiya, 1, No. 1 (1961)
L. P. Breslavets et al., 128-34. Changes in pollen grains in rye plants exposed to continuous gamma bombardment.
N. M. Berezina, V. A. Yazykova, 135-38. Significance of disturbance to metabolic reactions in radiation
damage to seeds (of the corn plant).
G. V. Radzievskii, 141-48. Dosimetry for external alpha radiation.
Radiokhimiya, 3, No. 2 (1961)
Yu. A. Kototov et al., 199-206. Sorption of long-lived fission products by soils and clayey minerals.
Atompraxis, 7, No. 5 (1961)
J. Baarli, K. Madshus, 167-70. Analysis of background radiation in the 0.08-1.7 Mev range measured by a
scintillation counter.
R. Tzschaschel, 170-72. Gamma-spectrometric investigation of fallout specimens by the gray wedge method.
H. Munzel, M. Hollstein, 177-78. Effect of shape of loop on the counting characteristics of a methane flow-
type counter.
H. Scharpenseel, 178-81. Effect of several material parameters on measuring efficiency in liquid scintillation
spectrometry.
Energia Nucl., 8, No. 4 (1961)
A. Persano et al., 287-94. Calculating safety factors and radiological shielding for nuclear power stations.
939
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Health Phys. 5, Nos. 1-2 (1961)
- 1-19, Suggested rules for radiation shielding.
E. Wagner, G. Hurst, 20-26. GM gamma dosimeter with low neutron sensitivity.
G. Brownell et al., 27-36. Large plastic scintillators for radioactivity measurements.
P. Harris, 37-44. Irradiation dose determination in an accident due to criticality at the Los Alamos laboratories
In 1958.
M. Randloph et al., 24-29. Decay of polonium-beryllium fast-neutron sources.
E. Ray, S. Hammond, 50-56. Use of alpha-pulse amplitude analyzer in dosimetric monitoring of surroundings.
E. Gupton et al., 57-62. Use of flat film badge at ORNL in criticality accidents.
A. Broido, J. Teresi, 63-69. Study of hazard associated with radioactive fallout. I. Determination of gamma
and beta dosage.
D. Gardiner, K. Cowser, 70-78. Removal of radioisotopes from low-activity industrial wastes.
P. Zigman, J. Mackin, 79-84. Premature decay of fission product mixtures. II. Rates of liberation of gamma-
energy and ionization in response to fissioning of U235 by thermal neutrons.
Health Phys., Nos. 3-4 (1961)
W. Lacy, 228-32. Some problems in deep-pit disposal of radioactive wastes.
H. Larson, 233-35. Pocket dosimeter counter.
C. Bernard et al., 236-43. Silver metaphosphate glass for x-ray measurements in fields of neutron and gamma
radiation.
E. Tochilin, R. Golden, 244-249. Investigation of relative sensitivity of photographic emulsions to beta and
gamma radiation.
L. Stephens et al., 267-74. Radioactive fallout and natural background radiation in the Sna Francisco Bay area.
J. Teresi, C. Newcombe, 275-88. Calculation of maximum tolerance concentrations of radiactive fallout in
water and air.
D. Summers, M. Gaske, 289-92. Maximum tolerable activity of fission products in air and water.
M. Rankin, 293-98. Air alpha activity badge.
F. Bradley, 298-301. Use of electrometer with vibrating-reed sensor as alpha counter.
B. Wheatley, 301-302. Integrating dosimeter with ionization chamber.
E. Geiger et al., 302-304. Simplified method for alpha-emitter autoradiography.
H. Wyker, 309-11. Maximum tolerable concentration of nonidentified radioisotopes in water.
R. Rosen, 311. Method for evaporating water fallout samples.
940
Jaderna Energie, 7, No. 5 (1961)
V. Stach, 146-50. Safety factors for overheating in fuel elements.
Kernenergie, 4, No. 4 (1961)
R. Reichel, 285-90. Study of de-excitation time in liquid organic scintillators.
Nucl. Power, 6, No. 62 (1961)
D. Brocardo, 67-69. Safety and reliability of scram circuits. 1.
Nucleonics, 19, No. 6 (1961)
P. Berry 62. Attenuation coefficients for gamma radiation.
P. Wickersham, L. Ostwald, 66 ff. Microwave detector for measuring thermal neutron flux.
Nukleonik, 3, No. 2 (1961)
M. Bormann et al., 85-92. Particle discrimination with the aid of scintillation detectors.
Radiation Res., 14, No. 3 (1961)
L .Skargard ,H .Johns, 231-60. Spectral flux density of scattered and primary radiation at 250 kv.
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L. Skarsgard et al., 261-80. Correction for iterative characteristics of.a scintillation spectrometer.
N. Barr et al., 291-95. Use of Fricke dosimeter for measuring photoelectric absorption.
Radiation Res., 14, No. 4 (1961)
A. Boni, 374-80. Polyacrylamide gamma dosimeter.
V. RADIOACTIVE AND STABLE ISOTOPES
TRACER TECHNIQUES. USES OF RADIOACTIVE RADIATIONS. DIRECT
CONVERSION
Avtomob. dorogi, No. 4 (1961)
V. G. Firstov, 22-23. Radiometric sensing of compacting of roadbed.
Vestnik akad. nauk Kazakh. SSR, No. 3 (1961)
V. I. Ryaldiovskii, 107-108. Nuclear radiations for disinfection of fur and leather raw materials.
Gazovaya prom., No. 4 (1961) [Gas industry]
V. A. Astakhov et al., 10-14. Automatic radioactive condensate bleed, type AKO-1.
Doklady akad. nauk SSSR, 137, No. 4 (1961)
I. N. Plaksin et al., 880-81. Neutron activation analysis applied to determination of tungsten content in
minerals and beneficiation products.
Doklayd akad. nauk Uzbek. SSR, No. 3 (1961)
V. P. Vasil'ev. Study of intermediate layer of an oxide cathode, with the aid of radioactive tracers.
Zavod. lab., 27, No. 4 (1961)
V. N. Fainberg, 411-13. Gamma-ray flaw detection of thick-walled parts by means of a scintillation counter.
Izvestiya akad. nauk Eston. SSR. Seriya fiz.-matem. i tekhn. nauk, 10, no. 1 (1961)
A. I. Karpov. 75-81. Experimental investigation of speed of particles and resistances in pneumatic conveying
by the tracer method.
Kozhev.-obuvnaya prom.,:No. 2 (1961) [Shoe and leather industry]
I. A. Mad, E. P. Mediis, 12-13. Radioactive instrumentation in extractive industry.
Razvedka i okhrana nedr, No. 3 (1961)
A. A. Ya. Doronin, 44-45. Experience in the use of radioactive techniques for delineating tectonic zones.
Sb. nauchno-issled. inst. osnovanii i podzemnykh sooruzh. akad. stroit. i arkhitek. SSSR, No. 43 (1961)
D. E Pol'shin , Hsi Chung-Han, 5-12 Gamma-ray method for investigating a planar field of soil density.
941
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Trudy Vsesoyuz. nauchno-issled. inst. veterar. sanitarii, 17 (1960)
V. I. Rogachev et al., 171-76. Ionizing radiations applied to the preservation of meats and meat products.
Trudy Moskv. energet. inst., No. 34 (1961)
N. N. Yakimov, L. G. Sherstnev, 315-22. Tracer studies of diffusion processes in an oxide cathode.
Trudy nauchno-issled. inst. asbesta, slyudy, asbestotsementnykh izdelii i proetktr. stroit. predpriyatii slyudyanoi
prom., No. 11 (1961) [mica and asbestos research]
M. G. Egorov, L. A. Sukhova, 114-18. Determination of B208 in synthetic boron micas, by the neutron absorption
method.
Appl. Radiation and Isotopes, 10, Nos. 2-3 (1961)
J. Dale et al., 65-71. Ion chamber for measuring t3- and y -radiation of standard radioactive preparations.
I. Possible applications and calibration.
J. Dale, 72-78. Ion chamber for measuring B - and y -radiation of standard radioactive preparations. II.
Instrument response to gamma radiation.
F. Carleton, H. Roberts, 79-85. Determination of specific activity of tritium-labeled compounds on paper
chromatograms with a servomechanism.
J. Puig, J. Dobo, 112-15. Radiochemical grafting by irradiation at low temperatures.
R. Platzman, 116-27. Total ionization of gases by high-energy particles.
H. Otto, M. Winand, 128-31. Sampling system for high-intensity gamma sources.
942
Atompraxis, 7, No. 6 (1961)
W. kolb, 146-50. Gamma radiography in boiler construction.
Jadema Energie, 7, No. 5 (1961)
B. Dolezel, 151-58. Effect of ionizing radiations on polymers.
Nucl. Engn., 6, No. 61 (1961)
P. Barrett et al., 230-32. Pulsed neutron sources.
Nucleonics, 19, No. 6 (1961)
B. Scott, W. Driscell, 48-52. Radiometric chemical analysis in automatic process control.
J. Cameron, J. Rhodes, 53-57. Radioactive sources in x-ray spectrometry.
- -, 88-89. A vessel with a seed irradiation facility.
T. Gregson et al., 90-93. Measurement of age of industrial components by the radioactive dating technique.
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ENGINEERING AND PHYSICS JOURNAL INZHENERNO -
FIZICHESKII ZHURNAL
THE JOURNAL COMES OUT MONTHLY IN TWELVE PRINTED FOLIOS.
The burden of the Journal's contents concerns scientific problems of deep significance for modern engineering.
In particular, the Journal publishes the results of theoretical and experimental physical research in the area of heat
and thermodynamics (heat exchange and mass balance, thermal conductivity theory, thermodynamics, physics Of
combustion, theory of dessication), physics of structural materials (soil mechanics, structural-mechanical and rheo-
logical characteristics of disperse media, heat transport in structural materials and enclosing structures), the ther-
modynamics of irreversible processes and its applications to transport phenomena in the presence of phase trans-
formations, chemical transformations, and nuclear transmutations, as relates to technological processes. The Journal
will also publicize engineering and technical methods for the solution of scientific and engineering problems.
The basic task of the Journal is to aid to the maximum the assimilation of the results of scientific physics re-
search into actual engineering practice, to contribute to closer coordination of the efforts of physicists and engineers
alike, as well as designers, in industrial enterprises and in-plant laboratories.
The Journal publishes articles and short notes, and contains the features: book review and current bibliography,
chronicle of outstanding events in the scientific life and activities of the USSR and other nations, a section of re-
view articles on the timeliest aspects of modem science and engineering.
The readership of the Journal embraces broad circles of scientific workers, professorial and educational institute
staffs, graduate students, undergraduates, engineers and technicians, workers in designing, drafting, and planning units,
and in-plant laboratories.
Subscriptions to the Engineering and Physics Journal will be processed by all municipal and district subsections
of Soyuzpechat', by communications offices and sections, and by all persons authorized for subscription, processing in
industrial enterprises, scientific institutions, and schools.
The subscription price is set at 8 rubles, 40 kopeks annually, 4 rubles 20 kopeks per half-year.
943
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Soviet Journals Available in Cover-to-Cover Translation
ABBREVIATION
AE
Akust. zh.
Astr(on). zh(urn).
Avto(mat). svarka
Byull. eksp(erim).
biol. i med.
DAN (SSSR)
Dokl(ady) AN SSSR
Derevoobrabat. prom-st'.
ntom(o1). oboz(renie)
Farmakol. (i) toksikol(ogiya)
FMM
Fiziol. zhurn. SSSR
(im. Sechenova)
Fiziol(ogiya) rast.
FTT
lzmerit. tekh(nika)
lzv. AN SSSR,
0(td). Kh(im). N(auk)
RUSSIAN TITLE TITLE OF TRANSLATION
Atomnaya energiya Soviet Journal of Atomic Energy
Akusticheskii zhurna) Soviet Physics ? Acoustics
Anti biotiki Antibiotics
Astronomicheskii zhurnal Soviet Astronomy?AJ
Avtomaticheskaya svarka Automatic Welding
Avtomatika i Telemekhanika Automation and Remote Control
Biofizika Biophysics
Biokhimiya Biochemistry
Byulleten' eksperimentarnoi biologii Bulletin of Experimental
i meditsiny Biology and Medicine
Doklady Akademii Nauk SSSR The translation of this journal is published
in sections, as follows:
Doklady Biochemistry Section
Doklady Biological Sciences Sections
(Includes: Anatomy, biophysics,
cytology, ecology, embryology,
endocrinology, evolutionary morphology,
genetics, histology, hydrobiology
Life Sciences microbiology, morphology, parasitology,
physiology, zoology sections) _
Doklady Botanical Sciences Sections
(Includes: Botany, phytopathology,
plant anatomy, plant ecology,
plant embryology, plant physiology,
plant morphology sections)
1 Proceedings of the Academy of Sciences
of the USSR, Section: Chemical Technology
Chemical Sciences Proceedings of the Academy of Sciences
of the USSR, Section: Chemistry
Proceedings of the Academy of Sciences
of the USSR, Section: Physical Chemistry
Doklady Earth Sciences Sections
(Includes: Geochemistry, geology,
geophysics, hydrogeology, mineralogy,
paleontology, petrography, permafrost
Earth Sciences sections)
Proceedings of the Academy of Sciences
of the USSR, Section: Geochemistry
Proceedings of the Academy of Sciences
of the USSR, Sections: Geology
Mathematics Doklady Soviet Mathematics
Soviet Physics?Doklady
(Includes: Aerodynamics, astronomy,
crystallography, cybernetics and control
theory, electrical engineering, energetics,
fluid mechanics, heat engineering,
hydraulics, mathematical physics,
Physics mechanics, physics, technical physics,
theory of elasticity sections)
Proceedings of the Academy of Sciences
of the USSR, Applied Physics Sections
(does not include mathematical physics
or physics sections)
Derevoobrabatyvayushchaya Wood Processing Industry '
promyshlennost'
Clecktrosvyaz Telecommunications
Entomologicheskoe obozrenie Entomological Review
Farmakologiya i toksikologiya Pharmacology and Toxicology
Fizika metallov i metallovedenie Physics of Metals and Metallography
Fiziologicheskii zhurnal im. I. M.
Sechenova Sechenov Physiological Journal USSR
Fiziologiya rastenii Plant Physiology
Geokhimiya Geochemistry
Fizika tverdogo tele Soviet Physics?Solid State
lzmeritel'naya tekhnika Measurement Techniques
lzvestiya Akademii Nauk SSSR: Bulletin of the Academy of Sciences
Otdelenie khimicheskikh nauk of the USSR: Division of Chemical Sciences
PUBLISHER
Consultants Bureau
American Institute of Physics
Consultants Bureau
American Institute of Physics
British Welding Research Association
(London)
Instrument Society of America
National Institutes of Health*
Consultants Bureau
Consultants Bureau
American Institute of Biological Sciences
American Institute of Biological Sciences
American Institute of Biological Sciences
Consultants Bureau
Consultants Bureau
Consultants Bureau
American Geological Institute
Consultants Bureau
Consultants Bureau
The American Mathematics Society
American Institute of Physics
Consultants Bureau
Timber Development Association
(London)
Massachusetts Institute of Technology*
American Institute of Biological Sciences
Consultants Bureau
Acta Metallurgica*
National Institutes of Health*
American Institute of Biological Sciences
The Geochemical Society
American Institute of Physics
Instrument Society of America
Consultants Bureau
TRANSLATION BEGAN
Vol. Issue Year
1 1 1956
1 1 1955
4 1 1959
34 1 1957
1 1959
27 1 1956
1 1957
21 1 1956
41 1 1959
106 1 1956
112 1 1957
112 1 1957
106 1 1956
106 1 1956
112 1 1957
124 1 1959
106- 1 1957-
123 6 1958
106- 1 1957-
123 6 1958
131 1 1961
106 1 1956
106- 1 1956-
117 1957
9 1959
1 1957
38 1 1959
20 1 1957
5 1 1957
1 1957
4 1 1957 .
1 1958
1 1 1959
1 . 1959
1 1952
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Declassified and Approved For Release 2013/09/25: CIA-RDP10-02196R000600070001-1
continued
lzv. AN SSSR,
0(td). T(ekhn). N(auk):
Met(all). i top.
lzv. AN SSSR Ser. fiz(ich).
lzv. AN SSSR Ser. geofiz.
lzv. AN SSSR Ser. geol.
Kauch. i rez.
Kolloidn. zh(urn).
Metalov. i term.
obrabot. metal.
Met. i top.
Mikrobiol.
OS
Pribory i tekhn.
eks(perimenta)
Prikl. matem. i mekh.
PTE
Radiotekh.
Radiotekh. i elektronika
Stek. i keram.
Svaroch. proiz-vo
Teor. veroyat. i prim.
Tsvet. Metally
UFN
UKh
UMN
Usp. fiz. nauk
Usp. khim(ii)
Usp. matem. nauk
Usp. sovr. biol.
Vest. mashinostroeniya
Vop. gem. i per. krovi
Vop. onk.
Vop. virusol.
Zav(odsk). lab(oratoriya)
ZhAKh Zh. anal(it). khimii
ZhETF
Zh. eksperim. i teor. fiz.
ZhFKh Zh. fiz. khimii
ZhMEI Zh(urn). mikrobiol.
epidemiol. i immunobiol.
ZhNKh
Zh(urn). neorganfich).
ZhOKh
Zh(urn). obshch(ei) khimii
ZhPKh
Zh(urn). prikl. khimii
ZhSKh
Zh(urn). strukt. khimii
ZhTF
Zh(urn). tekhn. fiz.
Zh(urn). vyssh. nervn.
deyat. (im. Pavlova)
I.
V
iiee Met. i top.)
lzvestiya Akademii Nauk SSSR: Seriya
Bulletin of the Academy of Sciences
fizicheskaya
lzvestiya Akademii Nauk SSSR:
of the USSR: Physical Series
Bulletin (lzvestiya) of the Academy of
Columbia Technical Translations
1
1954
Seriya geofizicheskaya
lzvestiya Akademii Nauk SSSR:
Sciences USSR: Geophysics Series
lzvestiya of the Academy of Sciences of the
American Geophysical Union
1
1954
Seriya geologicheskaya
USSR: Geologic Series
American Geological Institute
1
1958
Kauchuk i rezina
Soviet Rubber Technology
Research Association of British Rubber
Manufacturers
18
1
1959
Kinetika i kataliz
Kinetics and Catalysis
Consultants Bureau
1
3
1960
Koks i khimiya
Coke and Chemistry USSR
Coal Tar Research Association
(Leeds, England)
1
1958
Kolloidnyi zhurnal
Colloid Journal
Consultants Bureau
14
1
1952
Kristallografiya
Soviet Physics ? Crystallography
American Institute of Physics
2
1
1957
Metallovedenie i termicheskaya
Metal Science and Heat Treatment of
obrabotka metallov
Metals
Acta Meta I lurgica
6
1
1958
Metallurg
Metallurgist
Acta Metallurgica
1
1957
Metallurgiya i topliva
Russian Metallurgy and Fuels
Eagle Technical Publications
1
1960
Mikrobiologiya
Microbiology
American Institute of Biological Sciences
26
1
1957
Optika i spektroskopiya
Optics and Spectroscopy
American Institute Of Physics
6
1959
Pochvovedenie
Soviet Soil Science
American Institute of Biological Sciences
1
1958
Priborostroenie
Instrument Construction
British Scientific Instrument Research
Association
1
1959
Pribory i tekhnika eksperimenta
Instruments and Experimental Techniques
Instrument Society of America
1
1957
Prikladnaya matematika i mekhanika
Applied Mathematics and Mechanics
American Society of Mechanical
(see Pribory i tekhn. eks.)
Engineers
1
1958
Problemy Severa
Problems of the North
National Research Council of Canada
Radiotekhnika
Radio Engineering
Massachusetts Institute of Technology*
12
1
1957
Radiotekhnika i elektronika
Radio Engineering and Electronics
Massachusetts Institute of Technology*
2
1
1957
Stanki i instrument
Machines and Tooling
Production Engineering Research Assoc.
1
1959
Stal'
Stal (In English)
Iron and Steel Institute
1
1959
Steklo i keramika
Glass and Ceramics
Consultants Bureau
13
1
1956
Svarochnoe proizvodstvo
Welding Production
British Welding Research Association
4
1959
Teoriya veroyatnostei i ee primenenie
Theory of Probability and Its Applications
Society for Industrial and Applied
Mathematics
1
1956
Tsvetnye metally
Nonferrous Metals
Primary Sources
1
1960
Uspekhi fizicheskikh Nauk
Soviet Physics ? Uspekhi (partial translation)
American Institute of Physics
66
1
1958
Uspekhi khimii
Russian Chemical Reviews
The Chemical Society (London)
1
1960
Uspekhi matematicheskikh nauk
(see UFN)
(see UKh)
(see UMN)
Russian Mathematical Surveys
London Mathematical Society
15
1
1960
Uspekhi sovremennoi biologii
Russian Review of Biology
Oliver and Boyd
48
1959
Vestnik mashinostroeniya
Russian Engineering Journal
Production Engineering Research Assoc.
4
1959
Voprosy gematologii i perelivaniya krovi
Problems of Hematology and Blood
Transfusion
National Institutes of Health*
1
1957
Voprosy onkologii
Problems of Oncology
National Institutes of Health*
1
1957
Voprosy virusologii
Problems of Virology
National Institutes of Health*
1
1957
Zavodskaya laboratoriya
Industrial Laboratory
Instrument Society of America
25
1
1959
Zhurnal analiticheskoi khimii
Journal of Analytical Chemistry USSR
Consultants Bureau
7
1
1952
Zhurnal eksperimentarnoi i
theoreticheskoi fiziki
Soviet Physics?JETP
American Institute of Physics
28
1
1955
Zhurnal fizicheskoi khimii
Russian Journal of Physical Chemistry
The Chemical Society (London)
7
1959
Zhurnal mikrobiologii, epidemiologii i
immunobiologii
Journal of Microbiology,
Epidemiology and Immunobiology
National Institutes of Health*
1
1957
Zhurnal neorganicheskoi khimii
The Russian Journal of Inorganic Chemistry
The Chemical Society (London)
1
1959
Zhurnal obshchei khimii
Journal of General Chemistry USSR
Consultants Bureau
19
1
1949
Zhurnal prikladnoi khimli
Journal of Applied Chemistry USSR
Consultants Bureau
23
1
1950
Zhurnal strukturnoi khimii
Journal of Structural Chemistry
Consultants Bureau
1
1
1960
Zhurnal teknicheskoi fiziki
Soviet Physics?Technical Physics
American Institute of Physics
26
1
1956
Zhurnal vysshei nervnoi
deyatel'nosti (im. I. P. Pavlova)
Pavlov Journal of Higher Nervous Activity
National Institutes of Health*
1
1958
*Sponsoring organization. Translation through 1960 issues is a publication of Pergamon Press.
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Declassified and Approved For Release 2013/09/25: CIA-RDP10-02196R000600070001-1
SIGNIFICANCE OF ABBREVIATIONS MOST FREQUENTLY
ENCOUNTERED IN SOVIET PERIODICALS
FIAN Phys. Inst. Acad. Sc!. USSR
GD! Water Power Inst.
GITI State Sc!. -Tech. Press
GITTL State Tech. And Theor. Lit. Press
GONTI State United Sc!. -Tech. Press
Gosenergoizdat State Power Press
Goskhimizdat State Chem. Press
GOST All-Union State Standard
GTTI State Tech. and Theor. Lit. Press
IL Foreign Lit. Press
ISN (Izd. Soy. Nauk) Soviet Science Press
Izd. AN SSSR Acad. Sc!. USSR Press
Izd. MGU Moscow State Univ. Press
LEITZhT Leningrad Power Inst. of Railroad Engineering
LET Leningrad Elec. Engr. School
LET! Leningrad Electrotechnical Inst.
LETIIZhT Leningrad Electrical Engineering Research Inst. of Railroad Engr.
Mashgiz State Sc!. -Tech. Press for Machine Construction Lit.
MEP Ministry of Electrical Industry
MES Ministry of Electrical Power Plants
MESEP Ministry of Electrical Power Plants and the Electrical Industry
MGU Moscow State Univ.
MKhTI Moscow Inst. Chem. Tech.
MON Moscow Regional Pedagogical Inst.
MSP Ministry of Industrial Construction
Nil ZVUKSZAPIOI Scientific Research Inst. of Sound Recording
NIKFI Sc!. Inst. of Modern Motion Picture Photography
ONTI United Sci.- Tech. Press
OTI Division of Technical Information
OTN Div. Tech. Sc!.
Stroiizdat Construction Press
TOE Association of Power Engineers
TsKTI Central Research Inst. for Boilers and Turbines
TsNIEL Central Scientific Research Elec. Engr. Lab.
TsNIEL -MES Central Scientific Research Elec. Engr. Lab.-Ministry of Electric Power Plants
TsVTI Central Office of Economic Information
UF Ural Branch
VIESKh All-Union Inst. of Rural Elec. Power Stations
VNIIM All-Union Scientific Research Inst. of Metrology
VNIIZhDT All-Union Scientific Research Inst. of Railroad Engineering
VTI All-Union Thermotech. Inst.
VZEI All-Union Power Correspondence Inst.
NOTE: Abbreviations not on this list and not explained in the translation have been transliterated, no further
Information about their significance being available to us. ?Publisher.
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Declassified and Approved For Release 2013/09/25: CIA-RDP10-02196R000600070001-1
?
RESEARCH BY SOVIET EXPERTS
Translated by Western Scientists
RADIATION CHEMISTRY s. .
PROCEEDINGS OF THE FIRST ALL-UN1ON CONFERENCE
MOSCOW 1957
More than 700 of the Soviet Union's outstanding research scientists participated in this
conference sponsored by the Academy of Sciences and the Ministry of the Chemical
Industry.' Each of the 56 reports read in the various sessions covers either the theoretical or
practical aspects of radiation chemistry, and special attention is given to radiation sources
used, in radiation-chemical investigations.. The general discussions which followed each
report and -reflected various points of view on the problem under analysis are also included.
PRIMARY ACTS IN RADIATION CHEMICAL PROCESSES $25.00
RADIATION CHEMISTRY OF AQUEOUS SOLUTIONS -
(Inorganic and Organic Systems) $50.00
? RADIATION ELECTROCHEMICAL PROCESSES ? $15.00
THE EFFECT OF RADIATION ON MATERIALS INVOLVED IN
BIOCHEMICAL PROCESSES ?
RADIATION CHEMISTRY OF SIMPLE ORGANIC SYSTEMS
_
THE EFFECTOF RADIATION ON POLYMERS
RADIATION SOURCES
Individual volumes may be purchased separately.
$12.00
$30.00
$25.00
$10.00
. Special price for the 7-volume set $125.00
Tables of contents uflon request.
CONTEMPORARY_ EQUIPMENT
, FOR WORK WITH RADIOACTIVE ISOTOPES
Of the 110 isotopes produced in the USSR during
1958, 92 were obtained by neutron irradiation. The
methods and technological procedures used in the
production of isotopes and the preparation of
labeled compounds from them are reviewed in
detail. Shielding and manipulative devices for Work
with radioactive isotopes are illustrated as well as
described fully. These collected reports are of
interest to all scientits and technologists.concerned
with radioactive isotopes. -
Tables of contents upon moues!.
Durable paper covers 66 pp. illus. $15.00
PRODUCTION OF ISOTOPES
The eighteen papers which comprise this volume
were originally read at the All-Union Scientific and
Technical Conference on the AppIication of Radio-
active Isotopes, Moscow, 1957. The reports con-
sider the ploblems and achievements of Soviet
scientists in the production of radioactive isotopes
by irradiation of targets in Soviet reactors and
cyclotrons. ? Not only is this-work of Significance to
producers of isotopes, but many_ of the papers will
prove useful to isotope users as well.
Tables of contents upon request.
Durable paper covers 136 pp. illus. $50.00
' Payment in sterling may be made to Barclay's Bank in London, England.
CONSULTANTS BUREAU
227 West 17th Street ? New York H, N.Y. ? U.S.A.
Declassified and Approved For Release 2013/09/25: CIA-RDP10-02196R000600070001-1
Declassified and Approved For Release 2013/09/25: CIA-RDP10-02196R000600070001-1
Now available. . . an insight into the Soviet
problems and achievements in-. 4.
PRODUCTION of ISOTOPES
The eighteen papers which comprise this volume were
originally read at the All-Union Scientific and Tech-
nical Conference on the Application of Radioactive
Isotopes, Moscow, 1957. The reports consider die
problems and achievements of Soviet scientists in the
production of radioactive isotopes by irradiation of
targets in Soviet reactors and cyclotrons. Not only
is this work of significance to producers of isotopes,
but many of the papers will prove useful to isotope
users as well.
The Developthent, of Isotope Production in the USSR.
Certain Aspects of the Production of Radioactive Iso-
topes in a Nuclear Reactor.
Production of Radioactive Isotopes in a 10-Mev Deu-
teron Cyclotron.
Determination of Product Yields in Nuclear Reactions.
Spectrochemical Methods of Analyzing High-Purity
Materials Used in Reactor Construction and for
the Production of Radioisotopes.
Quantitative Spectral Determination of Impurities in
Radioactive Preparations.
The Production of Alpha-. Beta-, and Gamma-Sources
Using Oxide Films on Aluminum and Its Alloys.
Stable ,Isotopes Enriched by the Electromagnetic
Method.
Ultrahigh-Temperature Ion Source for Electromag-
netic Separation of Isotopes of Elements in the
Platinum Group.
Inhomogeneous Field Ivlass-Spectrometer for, Analy-
sis of Light-Element Isotopes.
The Relative Abundance of Palladium and Germanium
Isotopes.
Some Problems in the Theory of Isotope Separation.
Separation of Isotopes of Light Elements by Diffusion
in Vapors.
A Diffusion Column for the Separation of Isotopes.
A Fractionating Column for Preparing BF3 Enriched
in the Isotope B16.
An Investigation of the Separation of the Stable Iso-
topes of Light Elements.
The Separation of Carbon Isotopes.
Low-Temperature Methods for Separating Helium
Isotopes (He3 - fled).
1959 durable paper covers 136 pp., $56:00
CONSULTANTS BUREAU
227 WEST 17TH STREET NEW YORK 11 N Y
Declassified and Approved For Release 2013/09/25: CIA-RDP10-02196R000600070001-1