SOVIET ATOMIC ENERGY VOL. 41, NO. 6

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• Document Creation Date: January 4, 2017
• Document Release Date: September 23, 2013
• Sequence Number: 5
• Publication Date: June 1, 1977
• Content Type: REPORT

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Russian Original Vol. 41, No. 6, December, 1976
SATEAZ 41(6) 1037-1136 (1976) ?
'ATOIVIHAR 3HEPhill
(ATOMNAYA iNERGIYA)
TRANSLATED FROM RUSSIAN
CONSULTANTS BUREAU NEW YORK
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SOVIET
ATOMIC
ENERGY
Soviet Atomic Energy is abstracted or in-
dexed in Applied Mechanics Reviews, Chem-
ical Abstracts, Engineering Index, INSPEC?
Physics Abstracts and Electrical and Elec-
tronics Abstracts, Current Contents, and
Nuclear Science Abstracts.
Soviet Atomic Energy is a cover-to-cover translations of Atomnaya
Energiya, a publication of the Academy of Sciences of the USSR. '
An agreement with the Copyright Agency of the USSR (VAAP)
makes available both advance copies of the Russian journal and
original glossy photographs and artwork. This serves to decrease
the necessary time lag between publication of the original and
publication of the translation and helps to improve the quality
of the latter. The translation began With the first issue of the
Russian journal.
Editorial Board of Atomnaya Energiya:
Editor: 0. D. Kazachkovskii
Associate Editor: N,. A. Vlasov
A. A. Bochvar
N. A. Doll'ezhar
V. S. Fursov
N. Golovin
V. F. Kalinin
A. K. Krasin
V. V. Matveev
M. G. Meshcheryakov
V. B..Shevchenko
V. I. Smirnov.
A. P. Zefirov
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SOVIET ATOMIC ENERGY
A translation of Atomnaya Energiya
June, 1977
Volume 41, Number 6 December, 1976
CONTENTS
Engl./Russ.
ARTICLES
An Investigation of Resonance Absorption of Neutrons
in an RBMK-Type Grid - L. N. Yuroba, A. V. Bushuev,
A. F. Kozhin, M. B. Egiazarov, and P. M. Kamanin
1 037
387
Two-Dimensional Kinetic Calculation of Nuclear Reactor
by the Finite-Elements Method - N. V. Isaev, I. S. Slesarev,
N. E. Gorbatov, and A. P. Ivanov
1 042
31
Start-up Tests on the Efficiency of the Biological Protection
on Nuclear Power Stations Equipped with Water-Moderated
Water-Cooled Power Reactors - A. S. Iz'yurov, A. S. Kuzhil',
V. N. Mironov, A. I. Rymarenko, and S. G. Tsypin
1 046
395
An Experimental Study of the Way in Which the Internal Moderators
of Annular Fuel Elements Affect Resonance Absorption
in the Uranium - I. M. Kisir, V. F. Lyubchenko, I. P. Markelov,
V. V. Orlov, V. V. Frolov, and V. N. Sharapov
1 051
399
Formation of Vacancy Micropores during Bombarding of Nickel
by Similar Ions with Energy up to 300 keV - N. P. Agapova, I. N. Afrikanov,
V. G. Vladimirov, V. M. Gusev, V. D. Onufriev, and V. S. Tsyplenkov
1 055
402
Effect of Reactor Radiation on the Susceptibility of Austenite Steel
to Intercrystallite Corrosion - S. N. Votinov, Yu. I. Kazennov,
V. L. Bogoyavlenskii, V. S. Belokopytov, E. A. Krylov, L. M. Klestova,
and L. I. Reviznikov
1 058
405
Coherent Beam Instability in the IFVE Accelerator
- V. I. Balbekov and K. F, Gertsev
1-061
408
DEPOSITED ARTICLES
Multiorbit Induction Accelerators - A. A. Zvontsov, V. A. Kas'yanov,
and V. L., Chakhlov
1 066
413
Pressure Change in a Vessel with Saturated Water on Being Unsealed
-A. V. Alferov, V. V. Fisenko, and A. D. Shcherban'
1 067
413
Quantitative Estimates of the Energy of X-Ray Field Backscattered
from Air - F. L. Gerchikov
1068
414
Computation of the Radiation Field of a Unidirectional Point Source
of Fast Electrons by the Monte Carlo Method
- A. V. Plyasheshnikov and A. M. Kol'chuzhkin
1 069
415
Determination of Neutron Spectrum from Measurements with a Small
Number of Detectors - G. M. Obaturov and A. A. Tumanov
1 070
416
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CONTENTS
(continued)
Engl./Russ.
Floating Control of a Power Reactor with Respect to a Parameter
with Time Lag - B. G. Ogloblin and K. N. Prikot
1071
416
1072
417
1073
418
1076
420
1078
422
1080
422
1083
425
1085
427
1087
428
1089
430
1091
431
1094
434
1095
435
1097
438
1100
440
1101
441
1102
442
1104
443
1106
444
LETTERS
Sputtering of Metallic Surface by Fission Fragments
- B. M. Aleksandrov, I. A. Baranov, N. V. Babadzhanyants,
A. S. Krivokhatskii, and V. V. Obnoskii
The Composition of the Radiolysis Products of the System
CO2-H20(D20)-Oil Formed in a KS-150 Reactor
- M. I. Ermolaev, A. K. Nesterova, and V. F. Kapitanov ...... .
Determining the Thermal Power Outputs of Small High-Temperature
Nuclear Power Plants - A. I. EPtsov, A. K. Zabavin,
Yu. A. Kotelynikov, A. A. Labut, E. P. Lorin, I. P. Sviridenko,
and Yu. L. Shirokovskii
Influence of Irradiation on the Oxidation Kinetics of the Alloy
Zr +2.5% Nb - M. G. Golovachev, V. V. Klyushin,
and V. I. Perekhozhev
Influence of Boron on Radiation Embrittlement of Low-Alloy Steel
- V. A. Nikolaev and V. I. Badanin
Measuiement of the Ratio o-f(239Pu)/o-f(235U) for Neutron Energies
of 0.27-9.85 MeV - E. F. Fomushkin, G. F. Novoselov,
Yu. I. Vinogradov, and V. V. Gavrilov
Nuclear y Resonance Method for Investigating EI-69 Austenite Steel
Irradiated with y Quanta or Fast Neutrons - I. M. V'yunnik,
P. 0. Voznyuk, and V. N. Dubinin
Effect of Temperature on the Porosity of Nickel Irradiated with Nickel Ions
- S. Ya. Lebedev and S. D. Panin
Numerical y-Ray Albedo from Limited Sections of the Surface
of Reflecting Barriers - D. B. Pozdneev and M. A. Faddeev
Yields of 200 201T1,
T1, and 204T1 during Proton and Deuteron
Irradiation of Mercury - P. P. Dmitriev, G. A. Molin,
Z. P. Dmitrieva, and M. V. Panarin
Albedo of a Cylindrical Rod - V. V. Orlov and V. S. Shulepin
Operative Monitoring of Fission Products in Sodium Coolant of Fast Reactor
- V. B. Ivanov, V. I. Polyakov, Yu. V. Chechetkin,
and V. I. Shipilov
CONFERENCES AND MEETINGS
Regeneration of Fast-Reactor Fuel - A. F. Tsarenko
Meeting of Four Nuclear Data Centers - V. N. Manokhin
Meetings on the Compilation of Nuclear Data from Reactions
with Charged Particles and Data on the Structure of the Atomic Nucleus
- L. L. Sokolovskii
IAEA Symposium on the Design and Equipment of "Hot" Laboratories
- B. I. Ryabov
Second Seminar on Computer Simulation of Radiation and Other Defects
- Yu. V. Trushin
International Conference on "Ion-Exchange Theory and Practice"
- V. V. Yakshin
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CONTENTS
(continued)
BOOK REVIEWS
A. M. Petros'yants. From the Scientic Quest to the Atomic Industry.
Contemporary Problems of Atomic Science and Engineering
EngL/Russ.
in the USSR ? Reviewed by Yu. I. Koryakin
1108
446
V. A. Zuev and V. I. Lomov. Plutonium Hexafluoride
1109
447
? Reviewed by N. P. GW1iT
INDEX
Author Index, Volumes 40-41, 1976
1113
Tables of Contents, Volumes 40-41, 1976
1119
The Russian press date (podpisano k pechati) of this issue was 11/23/1976.
Publication therefore did not occur prior to this date, but must be assumed
to have taken place reasonably soon thereafter.
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ARTICLES
AN INVESTIGATION OF RESONANCE
ABSORPTION OF NEUTRONS
IN RBMK-TYPE GRID
L. N. Yuroba, A. V. Bushuev,
A. F. Kozhin, M. B. Egiazarov,
and P. M. Kamanin
UDC 539.125.5.173.162.3
The object of the present work is to obtain experimental data that would characterize the absorption of
resonance neutrons in grids of RBMK type of the Leningrad Atomic Power Station.
The computation of resonance absorption in such strongly hetrogeneous grids is a very complicated prob-
lem. The difficulties are associated with the consideration of not only energy but also the spatial distribution
of the flux of retarded neutrons. The presence of strong intrachannel retardation leads to a noticeable spatial
inhomogenity of the field of resonance neutrons in the cell. One of the possible directions in searching for the
solution of this problem is an experimental measurement of these dependences on the models of the active zone
of a reactor. The variation of the concentration of hydrogen in a hetrogeneous water film may have an effect
on the physical process in the intermediate thermal region of the neutron energy. Therefore, the integral para-
meters p", (48)/ of, which are sensitive to this region of the neutron spectrum and also the effective res-
onance absorption integral I2e5ff were measured.
In the present work we describe the experiments carried out by two experimental groups on RBMK-type
grids and present their results. The dimensions of the experimental assemblies, parameters of the fuel cas-
settes, and the procedures of measurements somewhat differ but the results were close, which permitted us to
arrive at consistent conclusions.
The height of one of the experimental assemblies of 25 cells in an RBMK-type reactor was 2 m. Cas-
settes of cylindrical form were placed in graphite stack with 25-cm steps. The fuel elements were prepared
from aluminum tubes (13.5 x0.65 mm), and filled with tablets of natural uranium dioxide with a density of 10.2
g/cm3 and diameter 12.15 mm (see Fig. 1).
A neutron beam from the horizontal experimental channel of the IRT-2000 reactor served as the source
for the subcritical assembly. The beam was directed along the hollow channel into the depth of a 1-m-high
graphite prism, which served as the base of the assembly and was used for forming spatial?energy distribu-
tion of neutrons entering into the assembly.
The axial distribution of neutrons in the assembly was measured by copper foils and Si-235U semiconduc-
tor detectors with cadmium coating and without it. The upper and lower boundaries of the region of asymptotic
spectrum of neutrons were determined and the location for subsequent experiments along the height was deter-
mined. The cadmium ratios for reaction 238U (n, ,y) in cassettes placed at the center of the assembly in the
second and the end rows were determined at this height. The values of cadmium ratios coincided within the
errors of measurements (? 1.5%). This permitted the conclusion that the leakage of neutrons does not effect
the results of measurements of Rd, p28, Cd, I? If I28 at the center of the assembly and the obtained values correspond
to the parameters of an infinite array within the indicated errors.
The parameters were measured with the use of indicators of about 1 mm in thickness prepared from
standard UO2 tablets filling the fuel elements. During the experiments, the indicators were placed in detachable
fuel elements, which were mounted in an experimental cassette in the place of the ordinary fuel elements. In
the measurements of the rate of reaction 238U(n,7) for resonance neutrons, a cadmium screen of 0.5 mm thick-
Translated from Atomnaya Energiya, Vol. 41, No. 6, pp. 387-391, December, 1976. Original article sub-
mitted July 16, 1975; revision submitted April 30, 1976.
This material is protected by copyright registered in the name of Plenum Publishing Corporation, 227 West 17th Street, New York, N.Y. 10011. No part
of this publication may be reproduced, stored in a retrieval system, or transmitted, in any form or by any means, electronic, mechanical, photocopying,
microfilming, recording or otherwise, without written permission of the publisher. A copy of this article is available from the publisher for $7.50.
1037
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Fig. 1. The transverse cross sec-
tion of the channel with cassette.
TABLE 1. Values of the Parameters Oc-
curring in Formulas (2) and (3).
Parameter
Value
Source of
information
ivo b
Kbl
St
S i (d ? 1mm)
Sst (d = 0.1mm)
Cpst /(Di
f (E)
275+5
0,3150+0,0054
1,335+0,005
1,045T-0,004
0,993+0,003
(w/o water)
0,996+0,003
(with water)
9,983(w/o water)
0,995(with water)
[51
131
Experiment
[31
Experiment
Computed by
N. I. Belousov
MIFI
TABLE 2. Results of Experiments
Medium
fuel
element
Arrangement of
fuel elements
K K. "2
zelf, b
x.
Kei= .Tir:
Kei (with water)
Kei (w /o water)
Graph-
ite
Single fuel
element
7,50+0,22
20,6+0,7
1,0
?
Row 1
5,52+0,16
15,2+0,5
0,736+0,007
Row 2
4,51+0,13
12,4T0,4
0,601+0,014
?
Row 3
4,60+0,12
12,7+0,4
0,613+0,020
Air
Value average
for cassette
5,16+0,15
14,2+0,5
0,688+0,010
?
Row 1
5,65+0,13
15,5+0,5
0,753+0,028
1,02?0,04
Row 2
4,90-T0,13
13,5-T0,4
0,653T-0,026
1,09+0,04
Row 3
4,93T-0,12
13,5+0,4
0,657+0,025
1,07T0,04
Water
Value average
for cassette
5,37+0,13
14,8+0,4
0,716+0,027
1,04+0,04
ness was used. The results of [1, 21, in which means of decreasing the effect of cadmium on the results of
measurement are indicated, were taken into consideration in choosing the scheme for arranging the indicator.
The standard method was used for determining If. The desired quantity was obtained by comparing the
rates of reaction in the indicator irradiated in the fuel elements of the cassette and in a uranium metallic foil
standard irradiated in the retarder at the distance of 10 cm from the cassette where the spectrum of epicad-
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TABLE 3. Results of Measurements with the
Second Assembly
Medium
around fuel'elf,
element
Arrangement of
fuel elements
,28 28
'eff Peffst
b
Row 1
0,770+0,015
16,2+0,7
Row 2 '
0,667T0,015
14,1+0,6
Row 3
0,648T-0,014
13,7T0,6
Air
Av. value for
cassette
0,731+0,015
15,4+0,7
Row 1
0,828+0,016
17,5+0,7
Row 2
0,717T0,014
15,1T0,7
'.ow 3
0,703T0,015
14,8T0,7
Water
A,:. value for
cassette
0,786+0,016
16,6+0,7
TABLE 4. Values of Some Parameters in
Formula (7)
Parameter Value
Source of
information
(18th 6
2,72+0,02
151
o2s 6
fth,
582,2+1,3
[5]
g25
0,976+0,002
[7]
y28 v25
Ce ' Ce
0,816+0,010
[8]
628*
0,034+0,02(with water)
Expt.
0,045+0 , 02 (w /o water)
*Ratio of number
of fissions in 238U to 235U.
TABLE 5. Values of (1) / (45) and p28
Parameter
Experi-
mental
system
Without
water
With
water
logs), \GP/
Assembly
in IRT
(7,50+0,13)?10-3
(6,16+0,04)? 10-3
Assembly
in F-1
(7,23+0,16)?10-3
(6,04+0,16)?10-3
228
Assembly 0,670+0,025
in IRT
0,441+0,009
1
mium neutrons is close to 1/E. The self-blocking coefficients for the standard t were determined experi-
mentally in [3]. The method of determination is based on the measurements of cadmium ratios for the standard
Rst and a thin uranium sample Ro:
IPsit = (Ro? 1)/(Rst ?1). (1)
The thin samples were prepared from aluminum foil of 0.1 mm thickness with a layer of natural uranium
of 0.25 mg/cm2 thickness. The corrections for the self-blocking of thin samples and for the difference of the
neutron spectrum in the retarder from 1/E spectrum were determined computationally.
The measurements of the intensity of reaction 238U (n, y) are based on recording of y radiation of 239Np
with an energy of 277 keV. A measuring system with a Ge(Li) detector was used for this purpose. The energy
resolution of the system at 277 keV was 2.4 keV.
Due to the unequal distribution of the radioactive nuclei in the sources, i.e., the indicators and the stan-
dards, errors may arise due to the different efficiency of recording of y quanta emitted from different seg-
ments of the source. In order to eliminate this effect an absorbing filter of variable thickness was placed be-
tween the source and the detector so that the efficiency of recording of y quanta with an energy of 277 keV was
equalized.
From the measurements of the activity of irradiated foil we obtain ai/ a st, the ratio of activities of the
indicator irradiated in one of the fuel elements of the cassette and the standard. The effective resonance inte-
gral of the fuel element of the i-th row of the cassette was determined from the formula
/eqf L.= MCI, (2)
where e is the true resonance absorption integral of 238U; Ki are coefficients that take account of the self-
blocking of the fuel element and the mutual screening of the fuel elements in the cassette, which were computed
from the formula
bl Si Ost Nst (E).
Ki= Ks
ast Sc7t (Di N,
Here K131 is the coefficient of self-blocking of the standard; t'stAD i is the correction taking account of the dif-
(3)
ference of the neutron fluxes at the locations of the i-th fuel element and the standard caused by the macrodis-
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tribution of neutron flux in the assembly; Nst/Ni is the ratio of the number of nuclei 238U in the standard and in
the indicator; f(E) is the computed correction for the departure of the spectrum of epicadmium neutrons in the
retarder from 1/E; Si and Sst are the correction for the self-absorption of 7 quanta with an energy of 277
keV in the indicator and the standard. The absorption coefficient of such y quanta in UO2 for the given geom-
etry of the measurements was determined experimentally and was 0.60 mm-I. The correction coefficient for
the self-absorption was computed from the formula given in [4]. The values of the parameters occurring in
formulas (2) and (3) are given in Table 1.
The values of 128 were determined for fuel elements of all the rows of the cassette, and In was deter-
effi effo
mined for single fuel element placed at the boundary of the cell. The ratios of gifo and 122 determine the co-
efficient of resonance blocking of the capture cross section of 238U in the fuel; Ki and K0 are, respectively, the
coefficients of mutual screening for the fuel elements in the fuel cassette. The effective resonance integral of
the fuel cassette was determined from the formula
E
e ffi
/Of 7 ni , (4)
where ni is the number of fuel elements in the 1-th row of the cassette; 1tt
2,8?. is the effective resonance integral
ei
of the fuel element of the i-th row of the cassette. The results are given in Table 2.
Another series of experiments were conducted on a subcritical assembly of 49 cells mounted in a wide
neutron beam (150 x150 cm) of the F-1 reactor. The height of the assembly was 1.8 m. Cassettes with diam-
eter of the fuel core of the fuel elements equal to 11.0 mm (casing 13.5 x1.0 mm) were investigated. The re-
gion of the asymptotic spectrum was determined by axial and radial measurements with indicators made of
238u, 1.15in, 239pu9 and
235U in cadmium filters and without them. The experiments showed that within the
assembly a region with 120 x120 x 100 cm dimensions has the asymptotic spectrum of neutrons that is charac-
teristic for this grid. In these experiments the resonance integral was determined from measurement of the
relative rate of absorption of epicadmium neutrons in the rods of the cassette and in a single rod placed in the
retarder at the boundary of the cell. The value of the resonance integral for the single rod was calculated
from the Hellstrand formula. Metallic foil of 10-fold depleted uranium of 0.09 mm thickness were used for the
measurements. The rate of capture reaction in 238U was measured on a NaI(T1) spectrometer from the y ra-
diation of 239U with an energy of 74 keV. In the analysis of the results corrections were introduced to take ac-
count of the small background from the radiation of the fission products. The effective resonance integral for
different fuel elements of the cassette was determined from a formula similar to (3):
/28
eff a st
/28 ?
ast (Di
effst
(5)
where Iafst =21.1 ? 0.8b for a rod of 11 mm diameter (computed from Hellstrand formula).
The resonance integral of the cassette was determined from formula (4). The results are shown in
Table 3.
Thus, the following conclusions can be made;
1. The effective resonance integrals for the two investigated types of cassettes differ insignificantly.
The somewhat larger value of the resonance integral in Table 3 is due to the smaller diameter of the uranium
cores of the fuel elements.
2. The filling of the fuel channels by water has a weak effect on the effective resonance integral of the
cassette.
In the experiments for the determination of p28 and (o-/ (of) in the assembly on IRT reactor the above-
mentioned indicators made of uranium dioxide and Ge(Li) spectrometer were used. The value of p28 was de-
termined from the measurements of the cadmium ratio Rd for the reaction 28U (n, 7) in the fuel elements;
p28 1/(1 - nd). (6)
The determination of Bpd is based on the measurement of radiation of 239Np with an energy of 277 keV from
the indicators irradiated in a cadmium screen and without cadmium. The irradiation was carried out in two
diametrically opposite experimental fuel elements of the cassette.
104,6
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The parameter ( crP)/ ( cri5) was determined from the measurements of -1/ radiation of 239Np with an
energy of 277 keV and the decay products of 143Ce with an energy of 293 keV (the procedure is described in [61).
(an 028
cth aNp
ith
(ar) 025 g25 aceC28 aaT.:KpR (7)
where crPth and a-43h are the cross sections of radiation capture in 238U and in the fission of 235U for thermal
neutrons; g25 is the Wescot factor; aNp and ac e are the radiation intensities of 239Np and143Ce indicators irradiated
in the fuel element; akep and at are the intensities of emission of 239Np and 143Ce indicators irradiated in the
thermal column; C28 ? 28 20 is a correction taking into consideration the contribution of the fission of
1+628 Yee/Yce
238U to the activity of 143Ce; Yee and lie are the yields of 143Ce in the fission of 238U and 235U. The indicators
were calibrated in the thermal column of the F-1 reactor of the I. V. Kurchatov Atomic Energy Institute.
The values of the parameters occurring in formula (6) are given in Table 4.
The ratio (48)/ (43) was measured also in the assembly on reactor F-1. The rate of reaction of cap-
ture in 238U was measured by depleted metallic uranium foil of 0.09 mm thickness; the y radiation of 239U with
an energy of 74 keV was recorded with a NaI(T1) spectrometer.
The background of the fission product under the peak of 74 keV was taken into consideration in accordance
with [9] and it comprised not more than 2% in the fuel and the thermal column. The rate of fission reaction of
235U was measured by foils of a dispersion alloy of aluminum and uranium enriched to 90% in 235U (mass con-
tent of uranium 17%) and having a thickness of 0.07 mm. The integral activity of the fission products was re-
corded. The mean values of (gen)/ (op \
/ for the cassette are shown in Table 5.
The results of the measurements show that the filling of the thermal channels by water leads to a reduc-
.
tion of (o8)/(of) and specially of p28 due to softening of the neutron spectra.
e f
In conclusion, one should note the increased reliability of the results presented here since they were ob-
tained on systems of different dimensions and with the use of different techniques and instruments.
LITERATURE CITED
1. A. V. Bushuev, L. N. Yurova, At. Energ., 27, No. 4, 334 (1969).
2. Y. Hachya, J. Nucl. Science and Technology, 9, 629 (1973).
3. L. N. Yurova et al., At. Energ., 38, No. 4, 24-5- (1975).
4. D. Watt and D. Reamsden, High Sensitivity Counting Techniques. Pergamon Press (1964), p. 277.
5. BNL-325, 3 Ed. V. I. N. Y. (1973).
6. L. N. Yurova et al., At. Energ., 32, No. 5, 412 (1972).
7. S. I. Sukhoruchkin, Atomic Technology Abroad, No. 8, 34 (1976).
8. L. N. Yurova et al., At. Energ., 36, No. 1, 51 (1974).
9. L. N. Yurova et al., At. Energ., 31, No. 6, 628 (1971).
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TWO-DIMENSIONAL KINETIC CALCULATION
OF NUCLEAR REACTOR BY THE
FINITE-ELEMENTS METHOD
N. V. Isaev, I. S. Slesarev, UDC 621.039.51.12
N. E. Gorbatov, and A. P. Ivanov
In theoretical investigations of nuclear reactors, it is often necessary to calculate the neutron-physical
characteristics of media consisting of heterogeneous regions of complex spatial configuration. Known calcula-
tional models of this type include, in particular, two-dimensional systems comprising an irregular set of hex-
agonal compartments with different physical properties.
In recent years, methods and procedures for the calculation of nuclear reactors consisting of hexagonal
compartments have been developed using both diffusional [1, 2] and kinetic [3] approximations. The use of a
compartmental approach is extremely convenient for nuclear-reactor designers, since it allows the necessary
information to be obtained for every compartment in the reactor. Natural refinements of the compartmental
model of a reactor are to use a more complex function to represent the neutron flux inside the compartments
(e.g.), by using series expansion with respect to some system of polynomials) or to adopt a more universal
triangular grid, which allows the cells of the grid to be reduced in size.
The present work proposes an approximate method of multigroup kinetic calculation of nuclear reactors
using a regular triangular grid. The calculation scheme is based on the finite-elements method [4, 5]. The use
of the kinetic equation allows the conditions at the outer boundary of the reactor to be accurately realized. In
the present paper, in contrast to [5], the operators of the Boltzmann equation are taken in non-self-conjugate
form, which is more convenient for computer realization. The use of a regular triangular grid leads to a sim-
ple three-point scheme for the calculation of a reactor consisting of hexagonal compartments. The proposed
method allows the solution to be found not only at the nodes of the calculation grid, as is usually the case with
numerical methods, but at any point within the compartment, since the function that approximates the neutron
flux inside the cell is known. The method is also suitable for precision calculations of nuclear reactors con-
sisting of hexagonal compartments.
Finite-Difference Grid
We consider a two-dimensional Itknetic equation in the form [6]
where
1 i 7)(114)(x, y, ,(1)(g)(x, y, (P)= K ff
LO(g) (x, y, Ix, (ID) =
1 g +1211
=1/-1 ? 1112 [cos cp 76T? + sin cp Vt,Vti CD(g)(x, y, 2
p=1 ?1 0
G 2.
X (x, y, VP )(x, y, T'); -01:1:"}(x, y, p., (p)=V?i) dp! d' vi x
X (x, VP) (x, y, (V);
/I =cos tu; tto=cos w cos w' +sin cc, sin tot cos(co ? go 9; F =1 , 2, ..., G is the number of the energy group; cu and
(19 are directions of flight of the neutrons;7(g) (x, y), Zp (x, y) are the total macroscopic cross section and the
?tot
(1)
Translated from Atomnaya Energiya., Vol. 41, No. 6, pp. 391-395, December, 1976. Original article sub-
mitted March 4, 1975; revision submitted December 26, 1975.
This material is protected by copyright registered in the name of Plenum Publishing Corporation, 227 West 17th Street, New York, N.Y. 10011. No part
of this publication may be reproduced, stored in a retrieval system, or transmitted, in any form or by any means, electronic, mechanical, photocopying,
microfilming, recording or otherwise, without written permission of the publisher. A copy of this article is available from the publisher for $7.50.
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Fig. 1
Fig. 1. Numeration of points in triangular cell.
Fig. 2. Compartmental model of a BFS-16-10 assembly (1/6). Size of hexagonal compartment ',under key"
13.5 cm: 1) compensating absorber; 2-5) low-enrichment zones; 6) high-enrichment zone; 7) lateral shield.
44.1
OS%
4011
Akpaddit
AAWAYA
AYAYWAWAVAVVAYAYA
Fig. 2
1,0
0,4
10 20 310 40 50
60 r,t cm
Fig. 3. Radial distribution of heat emis-
sion in the BFS-16-10 assembly. The
dashed lines show the diffusional calcula-
tion; the circles are experimental values;
and the continuous curves correspond to
the kinetic calculation; I) compensating
absorber; II) low-enrichment zone; III)
high-enrichment zone.
TABLE 1. Macroconstants of Compartments of BFS-16-10 As-
sembly
Type of0)
COMPart
ment
Itdt
mi - i
d
,,(020)
i f
v(2)
-tot
?
(2)):12)
v 1 -. 2
1
0,1913
0,1575
--
0,3359
0,2968
---
0,0266
2
0,1814
0,1683
0,0061
.0,2952
0,2877
0,0077
0,00877
3
0,1818
0,1686
0,00608
0,2952
0,2877
0,0077
0,00887
4
0,1818
0,1686
0,00608
0,2950
0,2877
0,0077
0,00887
5
0,1811
0,1680
0,00613
0,2942
.0,2868
0,00764
0,0087
6
0,1759
'0,1621
T0,00843
0,2894
.0,2800
0,0118
A,00842
7
0,2126
0,1967
0,00255
0,3324
.0,3267
0,00327 -
0,0128
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fission cross section for neutrons of the g-th group. EN (x, y, ?0) is the macroscopic cross section for
neutron transfer from the p-th to the g-th group; pco is the number of secondary neutrons formed in a single
fission episode; x (g) is the fraction of the fission spectrum consisting of neutrons of the g-th group; Keff is the
effective neutron multiplication factor.
As the boundary condition for Eq. (1) we take the condition of zero input of neutrons to the reactor
Vg)(x, y, p, (1))11" = --1 Q. We note in this connec-
tion, that with a maximum pressure of 4.3-10-6 mm Hg an instability of the 9th harmonic of the radial oscilla-
tions was observed sometimes; however, the increment in view of its small value could not be measured. Elec-
tron instabilities seem to be of low probability, as the buildup of an appreciable number of electrons in the
bunched beam with the stated parameters is impossible.
In determining the dependence of the increment on the chromaticity, the latter was adjusted by changing
the correction current in the square pole faces (Fig. 7). The current in the windings which focus and defocus
the units was chosen so that the chromaticity of the radial betatron oscillations remained constant. With a
change of current, the betatron frequency and the beam intensity were changed somewhat. The increment is re-
duced to the average frequency Qz =9.825 by the formula (see Fig. 5)
(10?Qz)/0.175. (4)
Normalization with respect to intensity was carried out by formula (3). Figure 7 coincides completely with the
previous results. Actually, the wall and ion instabilities are multireversible. For the oscillation mode of the
bunch shown in Fig. 2 and formula (1), the dependence of the increment on the chromaticity should be deter-
mined by the factor
QQ' )2 --2 dQ 172 if 9)2
A sy_1? (? CP ? .!!'" ? (p ? v ,
01' aP
(5)
where rrp2 is the mean-square phase length of the bunch. The first two terms of the expansion in series are
written here, so that this formula can be used when A 0.5. It follows from formula (5) and Fig. 7 that
117p-2 0.4. Processing of the oscillogram in Fig. 2 gives 1 (17 2 0.5.
Let us compare quantitatively the results obtained with the theoretical results. The increment of the
vertical instability can be written in the form
rpRAz (N? N) r e2gEz 172(4.0p
n'VQz (k Q z) L 4nadb3 (72-1) az (ar+ az) (4T2 -)- 1) f?
(6)
The numerical values of the variable parameters refer to an energy of 0.97 GeV: r=e2/mc 2 =1.54 ? p 10-flcm
is the classical radius of the proton; R =2.36- 104 cm is the average radius of the accelerator; N=2 ? 1012 is the
beam intensity; Nthr =0.4.1012 is the threshold intensity; Az is a factor which takes account of the dependence
of the increments on the chromaticity and is determined by formula (5) or from Fig. 7; -y =2.03 is the relativ-
istic factor; Q=9.825 is the betatron frequency; k=10 is the number of the harmonic; c =3 ? 1010 cm/sec is the
velocity of light; g=1.57 is the coefficient of linear expansion of the vacuum chamber due to corrugation; Ez =
0.85 is a factor which takes account of the ellipticity of the chamber cross section; o- =1.3 ? 1016 sec-1 is the
conductivity of the chamber wall; d= 0.04 cm is the thickness of the chamber wall; b=5.75 cm is the
half-height of the chamber; :7= 0.82 ? 105 mm Hg-1 ? sec-1 is the :lumber of ions formed by a single proton
per second at a pressure of 1 mm Hg; P = 6.9 -10-7 mm Hg is the pressure; az =1 cm is the half-height
of the beam; ar =2 cm is the half-width of the beam; wz =1.94 .105 sec-1 is the coherent oscillation frequency
and T =5 -10-6 sec is the effective time of interaction of the ions with the proton beam.
The first part of this formula, which takes into account the wall effect, differs from the well-known ex-
pression for the wall instability increment [4, 5] by the factors g, Ez, and 6 /d, where the latter is introduced
because the thickness of the skin layer. 6 is considerably greater than the wall thickness d. The effect of the
ions is taken into account in the second part of formula (6) in accordance with [3]. It should be noted that the
parameter T depends on the model used and the calculation is carried out with difficulty; the value taken is a
quite rough estimate.
When Az = 1, formula (6) gives Az =450 sec-1, and the wall contribution amounts to 510 sec-1; the ion con-
tribution is 60 sec-1. The corresponding experimental values (see Figs. 6 and 7) are: Az =360 20 sec-1, wall
contribution 400 sec-1 and the ion contribution is 40 sec-1, which are ,== 30% less than the calculated values. It
is possible that the discrepancy is explained by the scatter of intensity of the bunches. It was mentioned above
that scatter weakens the coupling of the bunches and leads to a reduction of the increments. In the calculation,
all the bunches were assumed to be identical.
The cause of the increase of the increments with increase of energy when W < 0.65 GeV (see Fig. 3)
could not be established. Although with a low energy the damping effect of the ions increases, this is inadequate
for explaining the observed relations. The chromaticity of the betatron oscillations in this region is small
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???-? 4-5), so that its effect is almost absent. It is possible that here there is strong cubic nonlinearity
of the magnetic field and a correspondingly higher threshold of instability, but the experimental verification of
this hypothesis was not undertaken.
Radial instability has much in common with vertical instability. Mainly the 10th harmonic is excited; the
form of the radial oscillations of the bunch is the same as in Fig. 2; the increments depend approximately iden-
tically on the energy (see Fig. 3). The radial increment increases with approach to complete resonance and
decreases with increase of pressure of the residual gas (see Fig. 6). The experimental and calculated values
of the increment differ by no more than a factor of two. However, the characteristics of the radial instability
are considerably less stable than the vertical instability. This can be seen, for example, from Figs. 3 and 6.
According to the first, the increment at 57 msec amounts to -100 sec-I, and according to the second, it is
-200 sec-1, although the principal parameters of the accelerator were unchanged. Certain data confirm that
the cause should be found first and foremost in the instability of the threshold.
Thus, the cause of coherent instability in the IFVE accelerator is the interaction of the beam with the
chamber walls, and the interaction with positive ions makes a relatively small stabilizing contribution. For
vertical instability, the calculated and experimental data coincide with an accuracy of up to 30%. In respect of
radial instability, the conclusions should be considered as preliminary, because the experimental data are in-
complete, although there are no factors which contradict the supposition of a single excitation mechanism for
both types of oscillations.
The authors thank V. L. Ushkov for assistance given by him during the measurement of the dependence of
the increment on the pressure.
LITERATURE CITED
1. C. Pellegrini, Nuovo Cimento, 64-A , 447 (1969).
2. K. F. Gertsev et al., IFVE. Preprint, SKU 74-85 (1974).
3. G. Hereward, CERN MPS/Int., DL-64-8 (1964).
4. V. L Balbekov and A. A. Kolomenskii, At. Energ., 19, No. 2, 126 (1965).
5. L. Laslett, V. Neil, and A. Sessler, Rev. Scient. Instrum., 36, 436 (1965).
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DEPOSITED ARTICLES
MULTIORBIT INDUCTION ACCELERATORS
A. A. Zvontsov, V. A. Kaslyanov, UDC 621.384.6
and V. L. Chakhlov
It is well known that the space charge of the beam limits the number of particles accelerated in a cycle.
Their number can thus be increased by simultaneously accelerating several beams in the one emitter unit.
Consequently, we must have several equilibrium orbits in the one emitter unit. We shall call accelerators of
this type multiorbit accelerators. The equilibrium orbits in the form of concentric circles are situated in the
one plane, while several such planes situated one above the other can be contained in a single unit. The field
strength at orbits of radii r01, r02, roi must satisfy the conditions
IT; (t)=21/z01 (t) for r =roi;
frz (t)> 2115(0 for r < roi;
175 (t) < 2Hz (t) for r > rob 0 < n (ro,) 1.1 MeV). The
specimens were screened from fission fragments and were weighed on a VLAO-100 analytical balance.
?During the tests (maximum duration 590 h) all the specimens became covered in a black film which ad-
hered to the metal. The dependence of the oxidation kinetics of the alloy on the test conditions is shown in Fig.
1. The results of a mathematical analysis of the data are listed in Table 1.
Translated from Atomnaya Energiya, Vol. 41, No. 6, p. 422, December, 1976. Original article submitted
December 19, 1975; revision submitted May 7, 1976.
This material is protected by copyright registered in the name of Plenum Publishing Corporation, 227 West 17th Street, New York, N.Y. 10011. No part
of this publication may be reproduced, stored in a retrieval system, or transmitted, in any form or by any means, electronic, mechanical, photocopying,
microfilming, recording or otherwise, without written permission of the publisher. A copy of this article is available from the publisher for $7.50.
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50
40
20
255
100 200 300 400
Test duration, h
Fig. 1. Oxidation kinetics of alloy Zr +
2.5% Nb in moist nitrogen, at various tem-
peratures. a) No irradiation; b) under ir-
radiation.
MG ? 600
TABLE 1. Oxidation Kinetics Constants
Oxidation
conditions
-
Temp-. ?C
Am = kt 1g T; ki
(Am)n = ii2s
k2
n
255
0,3
--
--
310
--
0,1
1,70
Underir-
330
--
0,2
1,72
radiation
350
0,8
1,89
405
1,8
1,91
425
--
3,5
1,96
290
0,7
--
--
330
0,7
--
--
Noir-
350
1,0
--
--
radiation
400
--
1,3
1,92
425
--
2.2
1,96
Analysis of the data after the tests shows that irradiation of the alloy Zr +2.5 mass % Nb by a flux of
neutrons in moist nitrogen increases the mass of the specimens by 20-50%. This effect may be due to the in-
fluence of neutron irradiation on the structure of the oxide film and on the composition of the medium.
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INFLUENCE OF BORON ON RADIATION
EMBRITTLEMENT OF LOW-ALLOY STEEL
V. A. Nikolaev and V. I. Badanin UDC 621.039.531
Interest in the influence of boron on the properties of ferrite?pearlitic steel for the casings of water-
moderated water-cooled power reactors has been stimulated by the following factors. In the first place, alloy-
ing with 0.002-0.005% of boron increases the hardenability, and hence the strength, of the steel, without appre-
ciably impairing its weldability [1]. Furthermore, information on the marked radiation embrittlement of steel
containing boron [2] reveals the necessity of assessing the possible role of this element as an impurity in steel
(,-10-3% or less).
In this connection we attempted to study the radiation embrittlement of steel 15KUMFA withabout 0.004%
of added boron; to elucidate the causes of the observed effects, we used boron of various isotopic compositions.
Method. The investigations were performed on metal from a 100-kg batch induction-melted in the labo-
ratory. When casting this into 16-kg ingots, a master alloy of Fe +10% B with a natural mixture of the isotopes
18B and 11B (18.4 and 18.6%), or with 95% enrichment in 18B or 11B, was added to the ladle.
To prepare the master alloy with enriched boron, we mixed elementary boron with powdered iron car-
bonyl; from the mixture we pressed tablets which were then sintered in vacuum. The melt was made with
Armco iron as charge. The chemical composition of the steel is shown in Table 1.
The ingots were drop forged and rolled to 10-mm sheet. The sheets were hardened from 960?C in oil and
tempered at 690?C. After heat treatment the material had the structure of finely dispersed sorbite with a pri-
mary austenitic grain size of 4-5.
The mechanical properties were determined on impact specimens 5 x5 x27.5 ram in size with a V-shaped
notch 1 mm deep and 0.25 mm in radius, and also on fivefold tensile specimens 3 mm in diameter. The liabil-
ity to radiation embrittlement was estimated [3] from the difference between the critical brittleness tempera-
tures Tc of the steel in its initial state and after neutron irradiation.
The materials were irradiated in the core and reflector of a VVR-M reactor with flux density ratios of
1:1 for fast neutrons (E> 0.5 MeV) and 1:10 for thermal neutrons. The method was described in detail in [3].
Experimental Results. Figure 1 shows the dependence of the rise in Tc for the steel on the isotopic com-
position of the boron and the fluence during irradiation in the core. After irradiation at about 50?C by a fluence
of 5. 1018 neutrons/cm2, the change in Tc for the steel was the greater, the greater the enrichment with 18B.
For the two extreme contents of 18B (about 5 and 95%), the shift in Tc differed twofold. A comparison with data
on the influence of irradiation on the yield point (Table 2) reveals that for radiation hardening of steel with the
same fluence there is no dependence on the isotopic composition of the boron.
When the fluence is increased to 5 ? 1028 neutrons/cm2 Tc increases by 190-200?C in materials of all com-
positions. From the results it follows that for steel with added 11B the graph of Tc vs fluence has the usual
ratio ATc adAF/ 3 (where F is the fluence in units of 1018 neutrons/cm) for the value A ?24. For the remaining
materials this relation does not obtain, showing that the saturation effect is attained earlier if 18B is present in
the steel.
When the irradiation temperature is raised to 300-350?C, the shift in Tc is much less, but in this case
also the embrittlement increases with the 18B content (Fig. 1, curve 3). The influence of irradiation temriera-
ture was investigated in more detail for steel with added natural boron. The results (Fig. 2) were compared
with the data for steel of similar chemical composition ',Table 1) but containing not more than 0.0005% B. The
Translated from Atomnaya Energiya, Vol. 41, No. 6, pp. 422-425, December, 1976. Original article sub-
mitted January 6, 1976.
This material is protected by copyright registered in the name of Plenum Publishing Corporation, 227 West 17th Street, New York, N.Y. 10011. No part
of this publication may be reproduced, stored in a retrieval system, or transmitted, in any form or by any means, electronic, mechanical, photocopying,
microfilming, recording or otherwise, without written permission of the publisher. A copy of this article is available from the publisher for $7.50.
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TABLE 1. Chemical Compositions of Mate-
rials
Boron Qontent, Other elements, lc,
mass le
0,004 "B
?
0,003 B
0,14 C; 1,72 Cr
0,005 1013
0,2 Ni; 0,81 Mo; 0,32 V; 0,2 Cu
0,0005 B
0,009 P
TABLE 2. Influence of Irradiation by a
Fluence of 5. 1019 neutrons/cm2 at 50?C on
Yield Point of Steel*
Boron content,
mass `10
00.2, kgfimm2
before irradiation after irradiation
0,004 "13
0,003
0,005 10B
*Tested at 20?C
75
75
76
96
95
97
AUC
80
40
JUG
120
80
40
0 100 200 300 400 0 100 200 300 400
Irradiation temp., 'C Annealing temp., 't
Fig. 2 Fig. 3
Fig. 1. Dependence of rise in Tc of steel on isotope composition of boron after irradiation. 1)
5 ? 1029 neutrons/cm2, 50?C; 2) 5. 1019 neutrons/cm2, 50?C; 3) ?1- 1029 neutrons/cm2, 300-350?C.
Fig. 2. Rise in Tc for steel with 0.003% boron (1) or no boron (2) vs irradiation temperature in
core [fluence (0.5-1) ? 1029 neutrons/cm21.
Fig. 3. Influence of annealing temperature on restoration of Tc for steel containing 19B after ir-
radiation with a fluence of thermal neutrons of 6.8.1029 neutrons/cm2 at 50?C.
extra embrittlement due to the boron falls rather rapidly as the irradiation temperature rises, especially be-
tween 150 and 250?C. This relation does not differ appreciably from that observed in steels with no boron ad-
ded [3, 5].
To elucidate the influence of boron on the embrittlement we studied the possibility of restoring Tc of ir-
radiated steel by postirradiation annealing. Experiments were performed on steel with added 19B; to increase
the contribution of this isotope to the embrittlement we irradiated the specimens mainly with thermal neutrons
(in the reflector).
Fig. 3 shows that after annealing for 1 h Tc is partially restored even at 200?C, while at 300?C it reaches
85-90%. The temperature range of restoration of Tc for steel with boron is typical of most steels of the fer-
ritic?pearlitic class [4, 5]. ,
The data show that the influence of boron merely intensifies the normal embrittlement, the external mani-
festations of which are well known.
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Fig. 4. Microstructure (a) and autoradio-
gram of boron distribution (b) of steel
15Kh2MFA.
Increase of embrittlement under the influence of boron probably occurs as a result of formation of frag-
ment nuclei with high kinetic energies (about 1.8 or 0.6 MeV) by the reaction 10B(n, a)7Li. Their retardation in
the matrix forms additional defects in the lattice. Owing to the large reaction cross section, the 10B is rapidly
burnt up (for a fluence of thermal neutrons of 5 ? 1020 neutrons/cm2 the burn-up is about 90%). Therefore, its
influence is manifested at comparatively low doses and is hardly appreciable in the conditions for the satura-
tion effect.
Radiation strengthening of steel does not depend on the 10B content. This is evidently because of the na-
ture of the distribution of boron, which can be seen by track autoradiography [6].
To study the distribution of boron* we used steel specimens with added "B. To obtain a coarse grain the
specimens were heat treated by heating under hardening to 1200?C, followed by tempering, as in the other cases
at 690?C. The resulting autoradiograms when compared with the microstructure (Fig. 4) showed that the den-
sity-of tracks is very nonuniform and is maximal at the boundaries of the former austenitic grains, which are
thus also sites, of preferential concentration of boron. The distribution of tracks left by alpha particles in the
autoradiograms simultaneously reflects the distribution of zones in which retardation of alpha particles and
lithium ions leads to an increase in the number of atomic displacements. Naturally, a macroscopic character-
istic such as the yield point, which is determined by the deformation resistance of the whole bulk of the metal,
cannot be influenced by such a local increase in defect concentration. Therefore the yield point depends almost
entirely on the uniformly distributed defects due to fast neutrons. At the same time, the most damaged zones
in the crystal lattice, adjoining grain boundaries, can apparently serve as sites of preferential formation of
crack nuclei, and consequently the appearance of such sites may influence the breaking strength of the steel.
Thus the role of boron in embrittlement of 'steel is essentially equivalent to an increase in fluence. It is
known that Te increases practically linearly with the fluence as the Ni, Cu, or P content of the steel increases
[3]. Therefore we can expect that the presence of boron should be more markedly manifested, the higher the
*The track autoradiography experiments were performed by N. V. Mishina and N. B. Odintsov.
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content of these elements in the steel. This means that when steel is alloyed, for example, with nickel, it may
be necessary to limit and control the boron impurity content in order to ensure high radiation stability.
LITERATURE CITED
1. C. Cottrell, J. Brit. Weld., 1, 315 (1954).
2. H. Myers and M. Grounes, in: Proc. of Third Intern. Conf., Geneva, 1964, A/conf. 28/P/420.
3. V. A. Nikolaev and V. I. Badanin, At. Energ., 37, No. 6, 491 (1974).
4. A. D. Amaev et al., Fourth Geneva Conference, Report No. 705 [in Russian], (1971).
5. C. Serpan and J. Hawthorne, Trans. ASME. J. Basic Engng., 89, No. 4, 877 (1967).
6. R. Fleischer, P. Price, and R. Walker, Science, 149, No. 3682, 383 (1965).
MEASUREMENT OF THE RATIO
7f(239Pu)/crf(235U) FOR NEUTRON ENERGIES
OF 0.27-9.85 MeV
E. F. Fomushkin, G. F. Novoselov, UDC 539.173.4:621.039.9
Yu. I. Vinogradov, and V. V. Gavrilov
The energy dependence of the ratio of the fission cross sections of 239PU and 25U for neutrons has been
studied by many investigators by various methods. However, at present there is a rather large disagreement
between the results. Even in the appraised data in the compilations of Davey [1], Byer [2], Greene et al. [3],
Sowerby et al. [4], and Kontshin et al. [5], it reaches 7-8%. The curves characterizing the ratio differ in shape,
especially at neutron energies of about 1-10 MeV. To refine our ideas of the structure of the graph of af(239Pu)/
7f(235U), it is advisable to carry out investigations by the same method over a wide range of neutron energies.
The preliminary results of measurements of the ratio of the fission cross sections of 239Pu and 235U,
given here, were obtained by the time-of-flight method with an underground nuclear explosion as the pulsed
neutron source. Similar measurements of comparatively well-studied characteristics also enable us to assess
the feasibility of using the method in other nuclear physics investigations.
The method of measurement was described in [6]; we shall merely mention its essential features. As the
fission-fragment detector we used a film of polycarbonate with a molecular mass of 90,000. Time-of-flight
scanning was effected by an electromechanical apparatus: One of its units was a drum with the polycarbonate
film cemented on, rotating at about 104 rpm at the moment of the neutron pulse. Layers of fissile isotopes
were arranged near the film in the neutron flux; between each layer and the film there was a slit-type fission-
fragment collimator.
With this method of measurement, the time resolution is governed by the rate of rotation of the drum, the
flight distance, and the width of the fragment collimator slit,
At/L-=-- Ax/5L,
where L is the flight distance, v is the linear velocity of the film relative to the collimator, and x is the col-
limator slit width.
In our measurements, the time resolution was 7.5 nsec/m (total width by half height). The influence of
scattered neutrons outside the direct flux was accounted for by additional collimators with layers of 235U and
239pu.
Calibration of the layers, i.e., measurement of the ratio of the effective numbers of fissile nuclei in the
layers (with allowance for the probability of passage of fragments through the collimator) was effected by
Translated from Atomnaya Energiya, Vol. 41, No. 6, pp. 425-426, December, 1976. Original article sub-
mitted January 21, 1976.
This material is protected by copyright registered in the name of Plenum Publishing Corporation, 227 West 17th Street, New York, N.Y. 10011. No part
of this publication may be reproduced, stored in a retrieval system, or transmitted, in any form or by any means, electronic, mechanical, photocopying,
microfilming, recording or otherwise, without written permission of the publisher. A copy of this article is available from the publisher for $7.50.
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7,25
NZ'
1,00
0,75 -
450
01,7 0,5
5 10
EmMe V
Fig. 1. Energy dependence of ratio of fis-
sion cross sections of 239Pu. and 235U.
Present authors' data; - - - -) estimate of
Sowerby et al. [4].
TABLE 1. Ratio af(239Pu)/crf(235U) vs Neu-
tron Energy
>
>
0
.,s,'
`,1..
.--.
b
--,
>
')
>m
.
tj
----
Error, 010
cud
e
11
d
d
z-
-
b
0,27
0,36
0,81
14,4
1,42
1,62
1,39
5,1
0,36
0,44
1,07
12,1
1,62
1,85
1,63
4,9
0,44
0,50
1,15
10,9
1,85
2,15
1,47
4,6
0,50
0,59
1,31
8,4
2,15
2,50
1,56
4,4
0,59
0,69
1,34
7,3
2,50
3,00
1,57
4,6
0,69
0,83
1,37
6,3
3,00
3,60
1,62
4,7
0,83
1,01
1,55
5,5
3,60
4,45
1,67
4,9
1,01
1,13
1,33
6,6
4,45
5,60
1,37
5,1
1,13
1,26
1,39
6,1
5,60
7,28
1;25
4,8
1,26
1,42
1,24
5,4
7,28
9,85
1,23
6,2
means of fission by thermal neutrons. The experimental unit, including the layers of 239Pu. and 235U, the col-
limator, and a small piece of detector film, was installed in a graphite prism 100 x100 X 100 cm in size. This
prism was irradiated by fast neutrons from a 235U critical assembly [7]. At the site of the test specimen, the
temperature of the thermal neutrons was 309 ? 18?K.
The fission cross sections for 0.0253 eV neutrons were 742.5 ? 3.0 b for 239Pu and 582.2 ? 1.3 b for 235U
[8]. The g factors were, respectively, 1.066 ? 0.014 [9] and 0.973 ? 0.003 [10].
The polycarbonate detector films were processed in identical conditions with 6.25 N NaOH solution. The
films were examined and the tracks counted in classes with an optical microscope. The results showed that the
total background of scattered neutrons in the range of times of flight under examination did not exceed 1.5%.
We made a correction for the contents of 239PU, 235U, and other fissile isotopes in the specimens. Since the prob-
ability of passage of fragments through the collimator depends on the angular distribution, we also made a cor-
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rection (about 1%) for the difference between the energy dependences of the angular anisotropy of fission of the
nuclei under investigation. The results of the measurement of the ratio crf(238Pu)/o-f (235U) for 20 neutron en-
ergy ranges (En.min and En. ) are shown in Fig. 1 and listed in Table 1. The quoted statistical errors cor-
respond to a confidence probability of 68% and were determined from the number of tracks due to fission frag-
ments in the corresponding intervals and the corrections. The calibration error (? 1.8%) was due to the error
of measurement for thermal neutrons and the error in the values used for the g factors and the fission cross
section for 0.0253 eV neutrons.
For comparison, Fig. 1 shows the curve recommended by Sowerby et al. [4]. We see that the results ob-
tained by the authors in the neutron energy range 0.5 -_En -4.5 MeV agree with the curve of the cross-section
ratio. The m arked c' viation from the recommended curve at higher energies may be due to the inadequate
energy resolution. However, there are certain results, e.g., those of Savin et al. [11], which agree with this
curve at high neutron energies (En> 4.5 MeV) as well. The discrepancy at low energies is apparently due to
background sources which were not taken into account.
Improvements to the method and further research will improve the accuracy and reliability of measure-
ments of the fission characteristics of heavy nuclei.
LITERATURE CITED
1. W. Davey, Nucl. Sci. Engng., 32, 35 (1968).
2. J. Byer, Atom. Energy Rev., 10, No. 4, 529 (1972).
3. N. Greene, J. Lucins, and C. Craven, Rep. ORNL-TM-2797 (1970).
4. M. Sowerby, B. Patric, and D. Mather, Ann. Nucl. Sci. Eng., 1, 409 (1974).
5. V. A. Kontshin et al., in: Nuclear Constants, [in Russian], No. 16, Atomizdat, Moscow (1974), p. 329.
6. E. F. Fomushkin et al., At. Energ., 39, No. 4, 295 (1975).
7. Yu. M. Odintsov, A. S. Koshelev, and A. A. Malinkin, At. Energ., 38, No. 4, 209 (1975).
8. S. Mughabhab and D. Garber, Neutron Cross Sections, Vol. 1, Resonance Parameters, BNL-325 (1973).
9. C. Wagemans and A. Deruytter, Ann. Nucl. Sci. Eng., 2, 25 (1975).
10. G. Hanna et al., Atom. Energy Rey., 7, No. 4, 3 (1969).
11. M. V. Savin et al., At. Energ., 29, No. 218 (1970).
NUCLEAR 7 RESONANCE METHOD
FOR INVESTIGATING EI-69 AUSTENITE STEEL
IRRADIATED WITH y QUANTA OR FAST NEUTRONS
I. M. VIyunnik, P. 0. Voznyuk, UDC 548-162 :539.16.04
and V. N. Dubinin
As is known, radiation damage produced by y and neutron irradiation affects the decomposition of aus-
tenite in the annealing of EI-69 steel [1, 2]. It was of interest to investigate more thoroughly the state of aus-
tenite in hardened steel immediately after irradiation. For this purpose, irradiated specimens were investi,
gated by using the nuclear y resonance (NGR) method (1VIOssbauer effect), which provides additional informa-
tion on radiation defects.
Hardened polycrystalline specimens of EI-69 steel (0.42% C, 13.35% Cr, 13.68% Ni, 2.08% W, 0.33% Mo
and 70.14% Fe) with a uniform composition (carbon-supersaturated austenite) were irradiated at room tempera-
ture with 1.2 MeV y quanta from radioactive cobalt 88Co (irradiation dose, 8.8. 1018 quanta/cm2) and fast neu-
trons from the VVR-M reactor at 60?C (mean fluence, 3.5 ? 1018 neutrons/cm2).
Translated from Atomnaya Energiya, Vol. 41, No. 6, pp. 427-428, December, 1976. Original article sub-
mitted January 21, 1976.
This material is protected by copyright registered in the name of Plenum Publishing Corporation, 227 West 17th Street, New York, N.Y. 10011. No part
of this publication may be reproduced, stored in a retrieval system, or transmitted, in any form or by any means, electronic, mechanical, photocopying,
microfilming, recording or otherwise, without written permission of the publisher. A copy of this article is available from the publisher for $7.50.
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Number of pulses
Source velocity.
Fig. 1. Absorption spectra of
iron atoms. a) In a steel matrix;
b, c) in steel irradiated with
quanta and fast neutrons, respec-
tively: d) in steel irradiated with
fast neutrons and annealed at
500?C over a period of 30 min.
The specimens for investigations based on the NGR method were prepared by electrolytic dissolution of
sheets of irradiated and nonirradiated steel. We obtained deposits with high concentrations of the carbide
phase and other nonmetallic high-dispersion phases, which cannot be observed by means of an x-ray diffracto-
meter. The thickness of the specimens (absorbers) was equal to 2.10-4 g/cm2 with respect to 57Fe. The pre-
pared specimens were investigated in an electrodynamic 1Vlossbauer spectrometer operating under constant-
acceleration conditions. The gamma radiation source was 57Co in a chromium matrix. The source and the ab-
sorber were kept a-, room temperature.
The results of investigations based on the NGR method are shown in Fig. 1. The velocity of the radiation
source relative to the absorber is laid off on the axis of abscissas, while the number of pulses per analyzer
channel is laid off on the axis of ordinates. The spectra were processed by means of a computer, using the
method of least squares. It was assumed that the lines had the Lorentz form.
The spectrum of hardened steel contains the usual austenite line with the width I' =0.53 0.03 mm/sec,
shifted by a =0.21 ? 0.03 mm/sec with respect to the line of sodium nitroprusside in Fig. la. Only negligible
line broadening, r =0.48 ? 0.03 mm/sec, occurs apparently as a result of y irradiation, which is seen in Fig.
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lb. In steel irradiated with fast neutrons, the NGR spectrum consists of the asymmetric line (Fig. lc) resul-
ting from the superposition of two lines (dashed curves): the singlet of the steel matrix with the width r=
0.52 ? 0.03 ram/sec and (5 =0.21 ? 0.03 mm/sec and a line with the width r =0.76 ? 0.05 mm/sec, the center of
which is shifted by (5 =0.62 ? 0.05 mm/sec with respect to the line of sodium nitroprusside.
Radiation defects develop in hardened EI-69 steel as a result of irradiation; most iron atoms are located
in normal regions of the crystal lattice that are not distorted by defects, so that the singlet of the steel matrix
is observed in experiments (Fig. 1 b and c). The broadening of this singlet may be connected with the concen-
tration nonuniformity caused by radiation defects in irradiated austenite. The appearance of the second, greatly
broadened line (c) indicates that some iron atoms enter the new phase formed under the action of neutron ra-
diation.
A much larger number of defects appears in hardened EI-69 steel irradiated with fast neutrons than in
steel irradiated with 7 quanta (in our case, 5.1020 and 1.2. 1017, respectively). For instance, such defects may
consist of vacancy clusters [3], which promote the development of precipitation particles in hardened steel. At
the initial stage of irradiation, an iron atom, bound to two carbon atoms, constitutes the basic precipitation nu-
cleus [4]. It can be assumed that this precipitation also takes place in hardened EI-69 steel under the action of
neutron radiation. Then, the line with the isomeric shift (5 =0.62 ? 0.05 mm/sec may be caused by the meta-
stable carbide phase MemCn, the isomeric shift of which is close to Fe5C2 [5].
As a result of annealing at 500?C over a period of 30 min, the metastable carbide phase in EI-69 steel ir-
radiated with fast neutrons passes into the stable phase Me23C 6, which is indicated by the appearance of lines
with the isomeric shift (5 =0.96 ? 0.03 mm/sec (Fig. 1d) in the spectra [6]. Precipitations of the carbide phase
Me23C were not observed in unirradiated specimens at this annealing temperature.
LITERATURE CITED
1. I. M. Vtyunnik, I. D. Konozenko, and M. P. Krulikovskaya, At. Energ., 37, No. 3, 245 (1974).
2. I. M. Viyunnik and M. P. Krulikovskaya, KIYaI-74-18 Preprint, Kiev (1974).
3. V. M. Raetskii and S. N. Votinov, Fiz. Met. Metalloved., 29, 284 (1970).
4. A. Damask et al., Philos. Mag., 22, 549 (1970).
5. Chemical Applications of Mossbauer Spectroscopy [Russian translation], Mir, Moscow (1970), p. 164.
6. P. 0. Voznyuk, L M. Vtyunnik, and V. N. Dubinin, Fiz. Met. Metalloved., 36, 1310 (1973).
EFFECT OF TEMPERATURE ON THE POROSITY
OF NICKEL IRRADIATED WITH NICKEL IONS
S. Ya. Lebedev and S. D. Panin UDC 621.039.51
The effect of helium on the formation of pores in nickel and the dependence of the radiation porosity on
the dose in irradiation with nickel ions at a constant temperature of the specimen (500?C) were investigated in
[1,
2].
We consider here the development of porosity at different temperatures, of the target. The method used
for preparing the specimens and the irradiation method were similar to those used earlier. Specimens of com-
mercially pure nickel, which had a thickness of 0.15 mm, were first annealed in a vacuum at 800?C over a pe-
riod of 1 h. Irradiation with 46-keV nickel ions was effected with a current density of 3 pA/cm2 to a dose of
1.6.1017 ions/cm2, which corresponded to approximately 40 displacements per atom [3]. The mean duration of
irradiation was equal to 2.3 h. The specimen temperature varied in the 350-700?C range.
Electron-microscope investigations of irradiated specimens have shown that vacancy porosity occurs at
specimen temperatures >400?C. The results obtained in processing the photomicrographs are given in Table 1.
Translated from Atomnaya. Energiya, Vol. 41, No. 6, pp. 428-429, December, 1976. Original article sub-
mitted March 9, 1976.
This material is protected by copyright registered in the name of Plenum Publishing Corporation, 227 West 17th Street, New York, N.Y. 10011. No part
of this publication may be reproduced, stored in a retrieval system, or transmitted, in any form or by any means, electronic, mechanical, photocopying,
microfilming, recording or otherwise, without written permission of the publisher. A copy of this article is available from the publisher for $7.50.
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TABLE 1. Investigation Results for Irra-
diated Specimens
4v/v17.
Ternp.,1:.
Pore density, .
cm3
Pore
size, A
Swelling
?I?
400
4,5.101'
20
0,22
450
1,85.1016
70
1,25
500
1,40.1016
100
2,45
550
1,05.1016
165
8,2
600
3-100
340
12,1
650
7-1013
550
5,6
700
5,75.1012
1600 .
1,25
2
10 .., 10-2
.? 5
no
.9 2
'Ei
5 10
a
o 5
2
400 450 500 550 600 650 700
Ternp.,
Fig. 1
100 300 500 700 900 1100
Pore dimension, A
Fig. 2
1300 1500 1700
Fig. 1. Temperature dependence of the swelling of nickel irradiated with Ni + ions to a dose of
1.6.1017 ions/cm2.
Fig. 2. Distribution function of pore dimensions in nickel irradiated with Ni+ ions at different
temperatures to a dose of 1.6. 1017 ions/cm2.
A large number of small pores with the mean dimension < dv> 20 A is observed at temperatures above 400?C.
Moreover; there is a large number of small dark spots, which, like the pores, are uniformly distributed over
the specimen's area under observation. The pores increase with temperature, and we find < dv > 1600 A at
700?C. At the same time, the density of pores < Nv> drops sharply with an increase in temperature. This in-
dicates that, at the low-temperature limit of pore formation, the incipient vacancy clusters are probably ther-
mally stable in irradiation with a constant flux of bombarding particles. The low mobility of vacancies is the
cause of the high density of small pores in the matrix. As the temperature rises, the vacancy mobility in-
creases, which results in more intensive pore development. Our experimental data agree with the theory of
uniform generation and development of vacancy porosity in irradiated metals [4].
Figure 1 shows the temperature dependence of swelling (AV/V) for nickel. The rather narrow swelling
peak has a maximum at 600?C. The maximum volume change corresponds to 0.5Tme?K. The swelling maxi-
mum observed at 600?C is in good agreement with data on nickel irradiation with 500-keV nickel ions [3]. The
noticeable swelling at temperatures below 500?C can be explained by the high density of small pores.
Figure 2 shows the distribution functions of pore sizes, obtained by processing histograms for different
temperatures. It is evident that the function broadens with an increase in temperature, and its maximum shifts
toward larger sizes. We observe a certain asymmetry of the curves, which indicates that the pores grow as a
result of fusion of small pores. This behavior agrees with the dependence observed for cold-rolled M-316
stainless steel, irradiated in the DFR reactor [5].
The distribution function indicates that, with an increase in the irradiation temperature, the pore size in-
creases, while the pore density diminishes. This confirms the assumption that generation of new pores does
not occur; rather, there is a continuous growth of the pores formed at the initial stage of irradiation.
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LITERATURE CITED
1. S. Ya. Lebedev, S. D. Panin, and S. I. Rudnev, At. Energ., 38, No. 6, 426 (1975).
2. S. Ya. Lebedev, S. D. Panin, and S. I. Rudnev, At. Energ., 39, No. 5, 362 (1975).
3. J. Delaplace, N. Aram, L. Le Naour, J. Nucl. Mater., 47, No. 3, 278 (1973).
4. Yu. V. Konobeev and V. A. Pechenkin, in; Problems of Atomic Science and Technology, Radiation
Damage Physics and Radiation Science of Materials Series [in Russian], Vol. 1, Atomizdat (1974), P. 41.
5. C. Cawthorne et al., in; Proc. Reading Conf. on Voids Formed by Irradiation of Reactor Materials,
Harwell, BNES (1971), p. 35.
NUMERICAL y-RAY ALBEDO FROM LIMITED
SECTIONS OF THE SURFACE
OF REFLECTING BARRIERS
D. B. Pozdneev and M. A. Faddeev UDC 539.122:539.121.72
Data about the distribution of reflected y quanta of a point isotropic source on the surface of a semi-in-
finite scatterer are given in [1-4]. However, no such information is available about barriers of finite thickness,
although it is of considerable interest for radioisotope instrument manufacture, radiometry, and other areas of
applications.
prEd
8
7
6
5
4
31_
2
a
6
145 279 662 1250 Ea, keV
13(E)
1,2-
1,0 ?
48
5
C6 ? 6
44 0 145 279 662 1250 Ea key
Fig. 1. Values of fl monodirectional (a) and isotropic (b) sources: 1) Pb; 2) Sn; 3) Fe;
4) concrete; 5) C; 6) Be.
Translated from Atomnaya Energiya, Vol. 41, No. 6, pp. 430-431, December, 1976. Original article sub-
mitted March 3, 1976.
This material is protected by copyright registered in the name of Plenum Publishing Corporation, 227 West 17th Street, New York, N.Y. 10011. No part
of this publication may be reproduced, stored in a retrieval system, or transmitted, in any form or by any means, electronic, mechanical, photocopying,
microfilming, recording or otherwise, without written permission of the publisher. A copy of this article is available from the publisher for $7.50.
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79 20
18 18
16
70
8
4
2
a
et. 41 42 0,3 V 7,0 2 5 10 al 0,2 0,3
16
14
2
I ta
8
16
14
12
10
8
6
4
2
42 43 0, 1 2 5 10 0,1 0,2 43 45 1 2 5 10
(f.p.1.)
Fig. 2. Values of a at E =1.25 (a, b) and 0.279 MeV (c, d): a, c) iso-
tropic source; c, d) monodirectional source; 1) Pb; 2) Sn; 3) Fe; 4) con-
crete; 5) C; 6) Be.
From analysis of data on the 7-ray albedo, obtained from Monte Carlo calculations according to a pro-
gram described in [3], it follows that the numerical 7-ray albedo a (r, d) from a circular region of radius r on
the surface of a barrier of thickness d can be described to within t 10% by the empirical formula
a (r, d)=-- a (co, co) ?exp (?Or)] (i?exp (?a (r)(d? c)11,
(1)
where a (00, 00) is the asymptotic value of the albedo from a semi-infinite scatterer made of the same material
when the primary-quanta source has a fixed energy of E0, and 13, a (r), and c are empirical quantities (Figs. 1
and 2).
Formula (1) was obtained from the results of calculations for point isotropic sources and monodirectional
beams normally incident upon the surface of a barrier at the point r =0 for E 0 =0.145, 0.279, 0.662, and 1250
MeV and for barriers made of Be, C, concrete, Fe, Sn, and Pb of varying thickness ranging from 0.1 to 5 free-
path lengths (f.p.1.). The value of c for an isotropic source is 0.5 free-path lengths of primary quanta of energy
E0, and c =0 for a monodirectional source. Using this formula, it is not difficult to find the number of reflected
7-ray quanta emitted from a surface portion of unit area, bounded by radii ri and r2 of concentric circles with
center at the point r=0.
LITERATURE CITED
1. B. P. Bulatov et al., Gamma-Ray Albedo fin Russian], Atomizdat, Moscow (1968).
2. 0. S. Marenkov, At. Energ., 21, No. 4, 297 (1966).
3. D. B. Pozdneev and M. A. Faddeev, Kernenergie, 16, No. 4, 105 (1973).
4. T. Nakamura and T. Hyodo, J. Nucl. Sci. Technol., 6, No. 3, 143 (1969).
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YIELDS OF zoon, 201T1, 202T1, AND 204T1
DURING PROTON AND DEUTERON
IRRADIATION OF MERCURY
P. P. Dmitriev, G. A. Molin, UDC 539.172.12
Z. P. Dmitrieva, and M. V. Panarin
Irradiation of mercury with protons and deuterons produces 200T1 (T1/2=26.1 h), 201T1 (T1/2=73 h)3202T1
(T1/2=12 days), and 204T1(3.78 yr), whose half-life makes them convenient for use in applied and research prob-
lems.
In this paper, the 200-202T1 yield is measured as a function of the proton and deuteron energy during ir-
radiation of thick mercury targets and theoretical yield curves are calculated for 204T1.
The irradiated samples were prepared from mercuric oxide, the conversion factor for the yield for Hg0
to the yield in metallic mercury is 1.17. The proton and deuteron energy was varied with copper stopping foils.
The methods employed to irradiate the samples and to measure the integrated irradiation current and the ac-
tivity of the isotopes were the same as in [1, 6] which reported on work also done on the cyclotron of FL
(Obninsk).
Isotopes 200-2?2T1 decay through electron capture (EC) and therefore their quantum radiation contains
strong components of IOC and LX rays produced by K and L capture as well as K and L conversion. Isotope
204T1 experiences decay (97.46%) and electron capture (2.54%) to the ground state of 44Pb and 2?4Hg, respec-
tively, and hence does not emit y quanta.
Table 1 gives the most intense components of quantum radiation accompanying the decay of 2?0-2?2T1 and
2?4T1. The gamma yield was obtained from the decay scheme given in [2, 3], taking the conversions into ac-
count. The yield of 7, LX, and KX quanta from 200-202T1 is calculated by the formulas
n(ICX)=-464,+04, ny alf,;
n (LX)=61,,wi,+ L (ny nicLny ictK i)
Here wk, WL. and ak,ctL are the fluorescence yield and the K- and L-conversion coefficients, respectively;
nici, is the number of L vacancies freed per K vacancy. The probabilities of K and L capture, ek and CL, were
calculated by the formulas and data of [4]; ? k, WL, and nKL are also given there. The values of ak and a L
were taken from [2, 3, 5], and the LX quanta were assigned the energy of the most intense transition Lai =
L3 ? M3. The yield of 10C and L quanta of 204T1 were obtained in [4].
The experimental yield curves for 200-202T1 and the theoretical curves for 204T1 are given in Figs. 1 and 2.
The reactions producing 200-202n and 204T1
are given in Table 2.
? Table 3 presents measured yields for given proton and deuteron energy. The calculation of the theoreti-
cal yield curves for 204T1 was similar to that in [6]. No data are available in the literature about the yield and
cross section for nuclear reactions producing
zoo-zozn and 204Ti.
As is seen from Table 3, when the protons and deuterons are slowed down the absolute error of the en-
ergy value increases. It thus follows that the path and energy of the particles are related by R ?E7/4, whence
dE/E=K dR/R or dE =KE dR/R, i.e., the absolute error is proportional to the absorbed energy.
Let us consider the production of 200-202T1 and 204T1 of high radioisotopic purity. Radioisotopically pure
204T1 and zozn, free of 200-202n, are obtained after appropriate cooling. Irradiation of mercury with protons and
Translated from Atomnaya Energiya, Vol. 41, No. 6, pp. 431-434, December, 1976. Original article sub-
mitted April 16, 1976.
This material is protected by copyright registered in the name of Plenum Publishing Corporation, 227 West 17th Street, New York, N.Y. 10011. No part
of this publication may be reproduced, stored in a retrieval system, or transmitted, in any form or by any means, electronic, mechanical, photocopying,
microfilming, recording or otherwise, without written permission of the publisher. A copy of this article is available from the publisher for $7.50.
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TABLE 1. Energy and Quantum Yield of 7,
KX, and LX Quanta
Iso-
tope
Energy of K, Quantum
K LX yield, 'To
References
200 TI
1205,7
367,97
Ka 70,14
Ko 80,71
LX 9,99
30,7
89,3*
71,3
20,7
34
12]
Present paper
It
2011
167,43
8,8*
[3]
Ka 70,14
69,8
Present paper
1(0 80,71
20,2
/1,X 9,99
45
n.?2 TI
439,4
92*
[3]
Ica 70,14
71,3
Present paper
K6 80,71
20,7
/-X. 9,99
32
Ot? It
204 Tl
Ka 70,14
1,14
[4]
Ko 80,71
0,33
[4]
L.,V 9,99
0,76
[4]
*7 -ray peaks used to measure the activity.
TABLE 2. Energy Thresholds of Reactions
2oo-2o2n and 204n,
of Production of MeV
Reaction
Isotope
20011
201T1
2021'1
204T1
pn.
3,26
1,20
1,91
1,16
p2n
9,53
9,02
p3n
17,31
15,45
dn
d2n
5,51
3,45
4,16
3,41
d3n
11,80
11,3
d4n
19,65
17,75
*The isotope is not produced in the given reaction.
reaction.
TABLE 3. Yield of 200-202n and 204T1
Origin and
energy of
particles,
MeV
Yield, ? Ciip A ? h
200T1
201T1
2021'1
204T1 *
(IlgJrp):
22,4+0,43
1020-F130
860-F110
21,9-F2,8
0,0077
20,3-F0,47
765-F98
685-F87
16,4-F2,1
0,0077
17,1-F0,52
450+57
410+63
10,8-F1,4
0,0071
14,3-F0,56
195-F25
160-F20
7,2-F1,0
0,0060
10,4-F0,61
15-F1,9
20,0-F2,5
1,6+0,2
0,0020
(1-11?-1-d):
22,5+0,41
1065-F135
595-F76
61,0-F7,8
0,10
21,1?0,43
790-F100
460+59
51,0A-6,5
0,098
20,2+0,46
725+93
400+51
46,4-F5,9
0,092
18,8A-0,49
530-F68
245-F31
43,8H-5,6
0,085
17,4-F0,50
380-F49
165-F21
36,5-F4,7
0,075
14,3+0,55
135-F17
55,0-F7,0
19,5-F2,5
0,043
10,1-F0,62
10,0-F1,3
5,0-F0,7
1,5+0,2
0,008
*The values of the 204T1 yield were calculated.
deuterons produces 198T1(T/ /2 = 5.3 h) and 199T1(T1 /2 = 7.4 h) whose activity becomes insignificant 3 days after the ir-
radiation. The content of the admixture 294T1 in the case of proton irradiation is smaller than in the case of
deuteron irradiation by a factor of - 10-20 and upon completion of the irradiation is 0.0008% for 200T1, 0.001%
for 291T1, and -0.04% for 292T1. Radioisotopically pure 299T1 can be obtained by the reaction 197Au (a, n) 299T1.
When gold was irradiated with 44-MeV alpha particles the 299T1 yield was 32 ACIJAA ? h, i.e., smaller by a factor of
-30 than when mercury was irradiated with protons and deuterons.
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1200
1100
1000 -
800
1. 700
,-- 600
500
400
300
200
100
28
24
20
15
12
8
4
8 12 16 20 24
Proton energy, MeV
Fig. 1
Yield 202T1, 204T1, liCi/pA ? h
1100 _
1000 -
900
,z 800
U 700
600
500
?-o
a)
400
300
200
100
4
8 12 16 20
Proton energy, MeV
Fig. 2
72
64
56
48
40
32
24
16
a
24
Yield 202T1, 204T1, ?Ci/tiA
Fig. 1. Yield of 20o-202T1 and 204T1 vs proton energy for thick mercury targets: 0) 200T1;.) 20111;
46,) 2o2n; _ _ __.) 204T1 (x 1000).
Fig. 2. Yield of 255-252T1 and 254T1 vs deuteron energy for thick mercury targets: 0) Mom I) 201n;
46,) 202n; _ _ .._) 204T1 (X200).
Isotopes 255-252T1 free from 2134T1 are obtained by irradiating mercury with alpha particles. Then, (axn)
PT,
reactions produce 205Pb (To 201pb =21.5h), t.,_ ih .9.4 h), 202mpbco
i =3.62 h), 252Pb (T1/2= 3 . 105 yr) which
are parent isotopes of 20
255-252T1. The isotope 2111Pb decays as follows: 2o2mpb_.202T1 (9.5%), 2o2mpb _.202pb
(90.5%). After -1.5 days only 255Pb and 25iPb remain in the lead fraction, and after -, 4 days, only 20opb, which
is in dynamic equilibrium with 255T1. Because of the long half-life, the 252Pb activity is negligible. High-purity
251T1 can be obtained by the reaction 253T1(p, 3n) 201pb, the reaction threshold being 16.5 MeV. The proton en-
ergy should not exceed the threshold of the reaction 253T1(p, 4n) 200pb, which is 25 MeV. Enriched mercury
isotopes can be used to obtain 255-252T1 of extremely high radioisotopic purity.
The authors thank G. N. Grinenko for his assistance in the work.
LITERATURE CITED
1. P. P. Dmitriev et al., At. Energ., 31, No. 2, 157 (1971); 39, No. 2, 135 (1975).
2. T. Comppa et al, Nucl. Phys., A163, 513 (1971).
3. R. Auble, Nucl. Data Sheets, 5, 561 (1971).
4. M. Martin and P. Blichert-Toft, Nucl. Data Tables, A8, Nos. 1-2 (1970).
5. R. Hager and E. Selzer, Nucl. Data Tables, 4, Nos. 1-2 (1968).
6. P. P. Dmitriev et al., At. Energ., 32, No. 5, 426 (1972).
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ALBEDO OF A CYLINDRICAL ROD
V. V. Orlov and V. S. Shulepin UDC 539.125.52:621.039.51.12
A system of multigroup albedo equations was obtained in [1] for the probability of reflection of neutrons
from a cylindrical rod or from an external spherical medium. As shown in [1, 2] in the two limiting cases (a
cylinder of very small and very large radius) the equations of [1] lead to a solution that is close to the exact one.
The objective of the present paper is to verify the exactness of the equations of [1] for a cylinder of interme-
diate radius.
An idea of the exactness of the system of equations in [1] can be obtained by solving the one-velocity
albedo equation
df3idR = s-20 (Z s +2s) +s2? (1,R) (1)
where 3 is the albedo, zs is the neutron scattering cross section, ze is the absorption cross section, and R is
the radius of the rod. The initial condition when R =0 is f3(0) =1. In the case zs =0 Eq. (1) is of the form
13 = [1 - exp ( - 4RZc)]/4REc? (2)
When Es 0 the solution of Eq. (1) can be rewritten as
= 1- raoR/(1? aiR ?a2R2-Fa3R3 I- ? ? ?)i ?
(3)
Substitution of Eq. (3) into Eq. (1) makes it possible to determine the coefficients an. The radial relation (3)
is analogous to the formula for the albedo of a cylindrical rod, obtained in [3]. Numerical calculations showed
that the solution (3) displays good convergence right up to RZ =R (Es +Ec) =2.
The exactness of Eq. (1) was verified by comparing the results of calculation by Eqs. (2) and (3) with the
exact results given in [4]. The calculation was performed for Rz over the interval [0; 2] for different ratios
h=Zs/E (Table 1).
According to Table 1, the exactness of Eq. (1) is satisfactory for all h when R 0.5 or for h> 0.7 when
R 2. As noted above, Eq. (1) also leads to correct results in the interval R for any h.
Equation (2) is inexact for large RZ and small h because under these conditions a large contribution to the
albedo is made by neutrons which do not experience collision in the rod and whose angular distribution is highly
anisotropic. Equation (1) can be made more exact by introducing the albedo of unscattered neutrons.
TABLE 1. Albedo of Rod for Different RZ
Exact solution
Solution of Eq. (1)
h
2,0
1,5
1,0
0,5 0,25
0,17
2,0
1,5
1,0
0,5
0,25
0,17
0,0
0,053
0,095
0,186
0,404
0,623
0,726
0,125
0,166
0,245
0,432
0,632
0,73)
0,2
0,115
0,165
0,263
0,482
0,683
0.773
0,179
0,233
0,317
0,504
0,689
0,775
0,4
0,199
0,256
0,363
0,574
0,749
0,823
0,270
0,319
0,407
0,590
0,753
0,825
0,6
0,324
0,389
0,499
0,686
0,823
0,877
0,386
0,437
0,529
0,695
0,825
0,878
0,8
0,542
0,604
0,694
0,824
0,906
0,936
0.568
0,623
0,705
0.827
0,907
0,936
1,0
1,0
1,0
1,0
1,0
1,0
100
1,0
1,0
1,0
1,0
1,0
1,0
LITERATURE CITED
1. V. V. Orlov, At. Energ., 38, No. 1, 39 (1975).
2. Yu. N. Kazachenkov and V. V. Orlov, At. Energ., 18, No. 3, 226 (1965).
Translated from Atomnaya Energiya, Vol. 41, No. 6, p. 434, December, 1976. Original article submitted
March 9, 1976.
This material is protected by copyright registered in the name of Plenum Publishing Corporation, 227 West 17th Street, New York, N.Y. 10011. No part
of this publication may be reproduced, stored in a retrieval system, or transmitted, in any form or by any means, electronic, mechanical, photocopying,
microfilming, recording or otherwise, without written permission of the publisher. A copy of this article is available from the publisher for $7.50.
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3. A. Amauyal, P. Benoist, and J. Horowitz, J. Nucl. Energy, 6, 79 (1957).
4. J. Stuart, in: Problems of Nuclear Energy [in Russian], No. 6, Izd. Inost. Lit., Moscow (1958), P. 71.
OPERATIVE MONITORING OF FISSION PRODUCTS
IN SODIUM COOLANT OF FAST REACTOR
V. B. Ivanov, V. I. Polyakov, UDC 621.373/374
Yu. V. Chechetkin, and V. I. Shipilov
To monitor the state of the active zone of fast reactors during operation and to predict the radiation sit-
uation when attending to the equipment it is necessary to know the level of the radioactivity of the fission prod-
ucts and the rate at which they are accumulated in the loop. Existing systems for monitoring the hermetic ity
of jackets with respect to delayed neutrons and radioactive gases do not directly yield such information.
The choice of radionuclides whose activity can be measured to solve the problem posed is determined by
the half-life, the character of their leakage through defects in the fuel jackets, and the contribution of their
radiation to the dosage rate from the equipment. The principal difficulty in measuring the activity of fission
products is determined by the fact that during the reactor operation this activity is smaller by a factor of 103-
10 6 than that of the short-lived activation isotope 24Na.
To ensure operative monitoring of the variations in the activity of selected nuclides in the loop, it is nec-
essary to carry out measurements right in the sodium channel, the duration of these measurements not ex-
ceeding several hours. Measurement by the usual one-detector and Compton suppression spectrometer sys-
tems with such ratios of the radioactivity monitored and interfering nuclides is possible only with very long
measuring times. Compton (CS) and summing Compton (SCS) spectrometers yield a decrease in the Compton
distribution by a factor of 100-1000 but in doing so they also have a significant loss in the efficiency of record-
ing the total absorption peak. Because of their more compact geometry contiguous semiconductors (duodes) in
the SCS mode make it possible to attain a lower efficiency loss than in the case of the SCS mode with dectors
separated by a considerable distance. Studies of various types of detectors showed that thin composite planar
detectors in the SCS mode are more sensitive than are detectors of the same total volume in the one-detector
mode [1, 2].
The block diagram of an SCS, which was tested in measurements in a sodium loop bypass connected to
the first loop of a BOR-60 reactor, is given in Fig. 1. The coolant flowed through a 16-mm tube. It took 100
sec for the sodium to arrive from the active zone. The detector was set up 2 m from the tube behind a 2-cm
collimator. The detector used in the experiment was a Ge(Li) duode consisting of two planar detectors, D1 and
D2, put together with a thin beryllium spacer. The total sensitive region was 12 cm3. The overall energy reso-
lution for an energy of 662 keV with input loads of 102 and 1 ? 105 was 5 and 6 keV, respectively. Energywindows
of 120-220 keV and 220-460 keV, respectively, were installed in the time channels of detectors D1 and D2 to record
the spectra of the sum of coincident energy in the 340-680-keV range. The resolving time of the coincidence
circuit was 75 nsec. The choice of the energy windows was determined by the desire to simultaneously monitor
nuclides 137Cs (662 keV) and 1311 (364 and 637 keV).
The y-ray spectrogram obtained with the spectrometer operating in the SCS mode (Fig. 2) in 150 min
exhibits total absorption peaks with an energy of 364.5, 511, 637, and 662 keV. The specific activities found
from the results of this experiment for 1311 and 137Cs, respectively, were (3 ? 0.6) ? 10-2 and (2 ? 0.4) ? 10-3 Ci/kg
sodium with a 24Na radioactivity of 48 ? 5 Ci/kg. In a one-detector mode with a detector of the same volume no
sought 7-ray peaks were resolved.
Thus, the SCS technique with a composite semiconductor detector allowed the fission-fragment nuclides
to be distinguished against the background of the 24Na activity in the first loop with a useful-to-interfering ac-
Translated from Atomnaya Energiya, Vol. 41, No. 6, pp. 435-436, December, 1976. Original article sub-
mitted April 20, 1976.
This material is protected by copyright registered in the name of Plenum Publishing Corporation, 227 West 17th Street, New York, N.Y. 10011. No part
of this publication may be reproduced, stored in a retrieval system, or transmitted, in any form or by any means, electronic, mechanical, photocopying,
microfilming, recording or otherwise, without written permission of the publisher. A copy of this article is available from the publisher for $7.50.
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/05'
A
3
Dl D2
5
2 -
3
4
7
No. of pulses detected
104
103
102
101
511 keV
300 400 500
Channel No.
700
Fig., 1 Fig. 2
Fig. 1. Block diagram of summing Compton spectrometer with Ge(Li) duode and measuring ge-
ometry: 1) piping with sodium coolant; 2) Ge(Li) duode; 3) fast charge-sensitive preamplifier;
4) logic circuit for selection and sampling of energy windows; 5) circuit for amplification and con-
trolled shaping based on two delay lines (1 x 1 ?sec); 6) summator-integrator; 7) pulse-height analyzer.
Fig. 2. -y--Ray spectrum of sodium coolant in the first loop of a BOR-60 reactor.
tivity ratio of the order of 104. Optimization a detector size and construction, improvement of the loading
properties of the spectrometric channel with lower counting loss due to pulse pile-up, and the choice of energy
windows in the spectrometric and measuring channels will make it possible to obtain a lower limit of measure-
meant for the summing Compton spectrometer and to determine the activity of other fission products.
The development of the SCS technique, in the opinion of the authors, will make it possible to ensure reli-
able continuous monitoring of the behavior of fission products in a sodium coolant and the development of de-
fects in fuel element jackets.
LITERATURE CITED
1. D. Walker and J. Palms, IEEE Trans. Nucl. Sci., NS-17, No. 3, 296 (1970).
2. V. Ivanov and V. Shipilov, Nucl. Instrum. and Methods, 119, 313 (1974).
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CONFERENCE AND MEETINGS
REGENERATION OF FAST-REACTOR FUEL
A. F. Tsarenko
A meeting of IAEA experts on the regeneration of fast-reactor fuel was held in Leningrad from May 17
to 21, 1976, with the participation of representatives of the USSR, France, Great Britain, the USA, the Federal
German Republic, Italy, Belgium and Japan. The agenda included a discussion of the state of the art in the re-
generation of fuel from active zones: storage and shipping to a processing radiochemical plant; cleansing fuel
assemblies from sodium; preparation for regeneration and the actual regeneration; waste handling.
The papers by the experts and the discussion showed that the level and scale of research on fuel regener-
ation in various countries are closely bound up with the level of development of the reactors themselves. The
fullest reports of all on the topics under discussion were presented by specialists of the USSR and France.
The following reactors are at present in successful operation in the world: BR-10, BOR-60, BN-350
(USSR); from 1967-1970 "Rhapsodie-Fortissimo" (France, 24-37 MW), from 1963 DFR [60 MW(T)] andfrom
1974 PFR [600 MW(T), Gt. Britain]. At the present time the following reactors are under construction or in the
planning stage: in the Soviet Union BN-600 and BN-1500; in the United States FFTF [440 MW(T)], 1979, Clinch
River [350 MW(T)], 1983, PLBR [1000-2000 MW(E)]; in France, jointly with the Federal German Republic and
Italy, "Super Phoenix" [1200 MW(E)]; and Italy PEC [130 MW(T)], 1979. The Federal German Republic planned
to start construction in 1976 of reactor KNK-2 [58 MW(T)] and in the same year Japan was to start construc-
tion of JOY? [100 MW(E)], and in 1983, MONHU [300 MW(E)].
The development of reactor BN-1500 in the USSR, and the rate at which plutonium is accumulated during
the regeneration of fuel from atomic power plants with thermal reactors (water moderated water cooled power
reactor, VVER, RBMK) permit the conclusion that the widespread introduction of fast reactors will begin no earlier
than 1990. The atomic power industry of the USSR will present atomic power plants with both thermal and fast
reactors, with the relative proportion of the latter gradually increasing. It is advisable to centralim the re-
generation of the fuel from such reactors in a radiochemical plant; according to calculations one plant should
handle fuel from atomic power plants with a total rating of 6-12 million kW, i.e., e.g., from 4 to 8 BN-1500
reactors. This requires the plant site be chosen in keeping with the conditions of long-term storage of the
radioactive waste as well as the safety of the population in the vicinity of the plant and protection of the envi-
ronment from radioactive contamination. If one proceeds from the premise that the power input will be deter-
mined by the plutonium build-up, reducing the cooling time of the fuel after discharge from the reactor from 3
yr to only 1 yr makes it possible for the rating of atomic power plants with fast reactors to be increased from
20 to 55 million kW, or 2.5 times, by the year 2000.
United States experts discussed the principal parameters of scientific-research and experimental-design
work on the regeneration of fuel from fast reactors with liquid metal coolants (LMFBR). These reactors are
looked upon in the USA as one means of satisfying the national energy requirements starting from 1990. A "hot"
experimental facility for regenerating fuel is to come into operation in 1988, and a pilot plant in 1995-2000.
France, which has been developing fast reactors for the past 18 years, is at present the only country with
industrial experience in the regeneration of spent mixed uranium-plutonium fuel (department AT-1 of the plant
in Cape Ag, and the experimental department of the plant at 1VIarcoule). In Gt. Britain the research is concen-
trated at the experimental plant at Dounreay.
The research in Italy has been directed at adapting the JTREC experimental plant at Rotondella with a
capacity of 10 kg oxide fuel for the regeneration of PEC reactor fuel. Similar work is being done in the Federal
German Republic on the MJLLJ experimental facility with samples of DFR reactor fuel.
Translated from Atomnaya Energiya, Vol. 41, No. 6, pp. 438-440, December, 1976.
This material is protected by copyright registered in the name of Plenum Publishing Corporation, 227 West 17th Street, New York, N.Y. 10011. No part
of this publication may be reproduced, stored in a retrieval system, or transmitted, in any form or by any means, electronic, mechanical, photocopying,
microfilming, recording or otherwise, without written permission of the publisher. A copy of this article is available from the publisher for $7.50.
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The Belgian research program envisages the construction of an experimental plant in the nuclear re-
search center in Mole by 1980; this plant is intended for experiments on cutting fuel elements on the thermal
oxidation processing of fuel, and on dissolution and gas scrubbing.
In the late 1980s Japan plans to build an experimental plant for developing a technology for the regenera-
tion of fuel from an experimental and a pilot reactor.
In all countries at the present time the aqueous extraction technology (extraction recovery of uranium
and plutonium from aqueous nitrate media with a solution of tri-n-butyl phosphate in inert solvents) is recog-
nized to be technically feasible, but it is necessary to solve problems associated, in the first place, with the
storage and shipment of mixed fuel, prepared for the operation preceding regeneration. In this plan the princi-
pal effort should be to create effective methods for removing metallic sodium from fuel assemblies, decladding
the fuel, dissolution, clarification, as well as for storing and shipping spent fuel elements.
Storing, Cleansing Spent Assemblies From
Coolant Residue, and Shipment
Of all the possible methods of heat removal during storage of spent fuel from fast reactors (cooling with
gas, sodium, bismuth-lead alloy, fused salts, organic materials) preference is given to sodium. Upon being
discharged from the reactor, assemblies are held in a sodium medium in a storage vessel inside the reactor,
and then for longer cooling are transferred to a sodium- and inert-gas filled (intermediate) storage vessel
outside the reactor, and finally put into a water pond. The assemblies of the Rhapsodie and Phoenix reactors,
for example, are held in the vessel inside the reactor for two months (the heat release drops to 0.4 and 6.0 kW,
respectively, per assembly), and then in a medium of argon (first) or sodium (second) are put into a storage
vessel outside the reactor with an inert gas or sodium, respectively.
Assemblies of the PFR reactor are cooled for 9 months in the internal storage vessel of the reactor, and
are then shipped to the reprocessing plant. Assemblies of the BN-350 reactor remain in internal storage for
two months until the residual release is reduced from 20-30 to 6-7 kW per assembly. In the external storage
vessel, consisting of a rotating drum with sodium, the assembly moves in an inert-gas medium. During the
transfer (-4 min) the temperature of the fuel element cladding reaches 480?C. The holding period does not
exceed the time between rechargings. When the heat release has been reduced to 3-4 kW per assembly, the
assembly is cleansed from sodium and then transferred to a water-filled cooling pond.
The most common method of cleansing assemblies from sodium is to treat them with water vapor with
nitrogen, argon, or carbon dioxide gas as gas carrier. An experiment using a lead bath to remove sodium and
to contain defective fuel elements (USSR) has demonstrated this method to be promising. However, some tech-
nical problems remain to be solved. To prevent radioactivity from entering the storage vessel from assem-
blies with defective fuel elements, it is deemed advisable to place the assemblies in hermetically sealed con-
tainers.
Problems due to the high level of heat release and radioactivity arise during shipment of spent fuel. The
heat release of one assembly may reach 5-10 kW, depending on the assembly size, the irradiation conditions,
and the cooling time. Present-day technology makes it possible to construct a shipping container designed for
a heat removal of about 40 kW, which means one container can take 6 to 10 assemblies. The mass of such a
container is 50-60 tons.
It was achnowledged at the meeting that the shipment of spent fuel in a sodium medium, as well as the use
of other heat-transfer media such as lead, have not yet been investigated sufficiently.
Decladding the Spent Fuel
Alongside the mechanical method of cutting fuel elements (France, Gt. Britain, USA) other methods have
been developed: laser cutting (USSR, Britain), melting the claddings of corrosion-resistant steel (USSR), etc.
Work is under way along such lines as constructing equipment for cutting individual fuel elements after dis-
mantling the assembly, as well as for cutting assemblies as a whole.
The decladding of spent fuel requires the solution of complex problems involved in the high heat release,
cleansing from gaseous and fugacious fission products, and nuclear safety. Experts of some countries (France,
USSR) voiced the opinion that the holding ("cooling") period for assemblies should be no less than 6-12 months.
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Dissolution of Spent Fuel and Clarification
of the Solution
Dissolution of uranium-plutonium oxide fuel in concentrated (8-12 M) nitric acid proceeds in two stages;
rapid dissolution of the bulk of the fuel and the slow dissolution of the residual fraction, constituting highly dis-
persed particles (from > 1 to 10 consisting of the fuel composition (UO2- Pu02), as well as alloys containing
fission products (Ru, Mo, Rh, Pd, Tc) add plutonium. The quantity of undissolved plutonium evidently depends
on the conditions of the fuel fabrication, irradiation, and dissolution. Therefore, the fuel is dissolved into two
stages, HF additives being used in the second stage (USSR, France). For this purpose apparatus of periodic and
continuous operation is being developed.
Most of the experts emphasized the need for thorough clarification of solutions prior to extraction. Work
is under way to develop reliable filters and filtering centrifuges; filtration and centrifuging can be employed as
two stages in the clarification process in any order.
In Dounreay a high-speed centrifuge (20,000 rpm) is used for clarification;and in department AT-1, a
pulsating filter is employed for that purpose. Soviet specialists propose flocculants in the solution clarification
stage.
Technology of Fuel Regeneration
It was acknowledged at the meeting that in the near future fuel from the active zone will be regenerated
by an aqueous-extraction technology of the "Purex process" type. The feasibility of highly efficient quantitative
regeneration of fuel by such methods is regarded as having been demonstrated experimentally.
Experience has been gained in regenerating mixed uranium-plutonium fuel on the experimental and pilot
scale. The most important experience has been accumulated in department AT-1 which has already regener-
ated about 1 ton of mixed oxide fuel from the Rhapsodie reactor with a burnup of up to 100,000 MW-days/ton.
The experimental department at Marcoule has also started regenerating mixed fuel from the active zone. Sev-
eral cycles have also been carried out at the MJLLJ plant in Karlsruhe (Federal German Republic) and at the
Dounreay plant.
A serious problem with adapting aqueous-extraction technology to the regeneration of active-zone fuel is
that of radiation decomposition of the organic extractant and nitric acid in the first extraction cycle. This prob-
lem is solved by using extraction apparatus with a short phase-contact time. Pulsating columns, and especially
centrifugal extractors, are just such apparatuses.
A very high plutonium content (up to 200 kg/ton) presents problems of accomplishing the complete.simul-
taneous extraction of plutonium and uranium, preventing the formation of a third phase, salt-free separation of
plutonium from uranium, monitoring and computing the plutonium content in solutions in conformity with the
safety requirements and the system of guarantees, and attaining discharge concentrations of plutonium in the
technological waste.
An interesting method is that of electrochemical selective reduction and re-extraction of plutonium in the
stage of separation from uranium. This method has been successfully tested in the regeneration of fuel
samples at the MJLLJ plant in the Federal German Republic; there are plans to introduce the method in the
WAK plant (Federal German Republic) and in Marcoule.
Work onthe fluoride method of fuel regeneration is under way at present in the USSR, France, and Japan.
The state of the development of this method is such that it cannot be introduced into industry. The basic prob-
lems which must be solved are connected with attaining a high degree of separation of uranium and plutonium,
deeply purifying plutonium from fission products, and completely extracting uranium and plutonium from the
final product. Putting the fluoride method into industrial use requires an extensive program of scientific re-
search and testing and design work and technological investigations. Fuel from the BOR-60 and Rhapsodie reac-
tors with a short holding time (3-6 months) has been regenerated in single operations in the Fregat (USSR) and
Attila (France) pilot plants, demonstrating the basic feasibility of the gaseous fluoride technology.
Method of Decontaminating Waste Gases
It is known that gaseous wastes of radiochemical reprocessing plants are the major source of radioactiv-
ity entering the environment. The need to reduce the radioactive discharges into the atmosphere requires the
introduction of efficient gas scrubbing systems in the plant. The state of the technology for trapping iodine,
krypton, xenon, tritium, and 14C was discussion at the meeting in these terms. The iodine trapping methods are
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in the pre-industrial stage at present but none of them has found universal application. These are the "wet"
methods [alkaline scrubbing, scrubbing with mercury nitrate solution, "Iodox process" - scrubbing gasses with
fuming (concentration of more than 20 M) nitric acid] and dry methods based on the use of filter media in which
silver salts are the active reagents. In eliminating krypton, more attention is paid to methods of cryogenic
distillation in comparison with methods of absorption with fluorocarbons.
As for the elimination of tritium, only attempts are being made to solve the problem. A method is being
developed in the Federal German Republic and France for localizing (and building up) tritium in recirculating
aqueous solutions of the main regeneration processes. Even if tritium is successfully concentrated in a small
volume of waste, the problem of storing and eliminating waste will remain.
In plants regenerating fast-reactor fuel the content of radioactive isotopes and plutonium will be signifi-
cantly higher than in thermal-reactor fuel. Therefore, the ratio of the radioactivity discharged into the en-
vironment to the activity in plants after the regeneration of fast-reactor fuel should be one-thousandth of that
in plants regenerating thermal-reactor fuel. To attain this level it is necessary to make a substantial im-
provement in the methods of localizing radioactivity in all stages of regeneration, to prevent losses of pluto-
nium, and to develop effective methods for trapping gaseous and fugacious fission products.
Waste Disposal
The general consensus is that the safe disposal of waste from the regeneration of fast-reactor fuel will
be based on methods which have already been accepted or are being developed for the fuel cycle of thermal
reactors. Most programs are based on vitrification, which is recommended for solutions with a heat release
of less than 5 ? 104 W/m3. For fast reactors it is necessary either to increase the holding of fuel for regenera-
tion to more than a year, to mix the waste from fast and thermal reactors, or to develop hard matrices allowing
storage at higher temperatures.
MEETING OF FOUR NUCLEAR DATA CENTERS
V. N. Manokhin
Four nuclear data centers held their regular (12th) meeting in Vienna on April 26-27, 1976. It was at-
tended by representatives of the National Neutron Cross Section Center (Brookhaven, USA), Neutron Data Com-
pilation'Center (Saclay, France), Nuclear Data Center (Obninsk, USSR), Nuclear Data Section (IAEA, Austria),
as well as Rumania and Poland. Brief reports on the work of each center over the previous year were read at
the meeting.
The National Neutron Cross Section Center is engaged in work on Series V of the evaluated nuclear data
file ENDF/B. The second volume of the new BNL-35 atlas has been completed. In 1975 evaluated data on fis-
sion products and reactor dosimetry were turned over for general use in the IAEA in 1975.
The Neutron Data Compilation Center has done a great deal of work on creating a SINDA bibliographical
catalog on collecting numerical data and on writing a program for data format conversion.
The Nuclear Data Section prepared the SINDA-76 catalog for publication, having previously eliminated
redundant and erroneous information. The CINDU-11 catalog of nuclear data possessed by the NDS has been
published. And WRENDA-76, a register of inquiries for nuclear data, is being prepared for publication.
Since April 1975 the Nuclear Data Center (NDC) has recorded 75 papers on magnetic tape. In all, to the
present time it has recorded some 300 out of a total of 450 papers, containing numerical data, published in
1959-1975. The evaluated data (complete files) of a number of isotopes have been handed over to the IAEA.
Four "Nuclear Constants" compilations were published and 110 inquiries were satisfied in 1975. The NDC has
prepared for publication the proceedings of the Third All-Union Conference on Neutron Physics. The evaluation
of all cross sections of nickel and chromium has been completed.
Translated from Atomnaya Energiya, Vol. 41, No. 6, pp. 440-441, December, 1976.
This material is protected by copyright registered in the name of Plenum Publishing Corporation, 227 West 17th Street, New York, N.Y. 10011. No part
of this publication may be reproduced, stored in a retrieval system, or transmitted, in any form or by any means, electronic, mechanical, photocopying,
microfilming, recording or otherwise, without written permission of the publisher. A copy of this article is available from the publisher for $7.50.
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The 19th meeting discussed the state of the computer library of experimental neutron data in exchange
format (EXFOR). At the present time this library contains more than 1,700,000 lines of information on mag-
netic tape - numerical results and brief descriptions of the conditions of many experiments on neutron physics.
The meeting also considered problems pertaining to the completeness of the data library, data exchange, errors
in the magnetic tape recordings, and the introduction of changes suggested earlier in the EXFOR format. Some
problems of the SINDA bibliographic catalog were also considered (ensuring the completeness of the abstracts,
the connection with the INIS system, the periodicity of publication, etc.).
The meeting recommended that all centers inform each other about the existence of evaluated data, de-
scriptions of evaluations, and results of comparison of the evaluated data of the various libraries.
The results of the meeting showed that the international cooperation on the exchange of experimental
neutron data is developing. The exchange of evaluated neutron data is increasing.
The next meeting of the four nuclear data centers will be held in Obninsk in April, 1977.
MEETINGS ON THE COMPILATION OF NUCLEAR
DATA FROM REACTIONS WITH CHARGED
PARTICLES AND DATA ON THE STRUCTURE
OF THE ATOMIC NUCLEUS
L. L. Sokolovskii
The meeting of consultants on data from reactions with nuclear particles, organized by the Nuclear Data
Section of the IAEA, was held in Vienna from April 28 to 30, 1976, with the participation of representatives of
Gt. Britain, Poland, Rumania, the USSR, the USA, France, the Federal German Republic, and Japan. The
agenda was purely technical: the index of bibliographical data, the range of compilation, computer file, keywords,
dictionaries, improvement and coordination of dictionaries, and the principal rules of EXFOR for reactions
with charged particles.
As a result of the work of the Meeting an international network was established of Centers and groups
participating in the exchange of numerical, bibliographical, and evaluated material on data from reactions with
charged particles.
It was decided that the next meeting on the compilation of data from reactions with charged particles
would be held in the USSR after tha All-Union Conference on Neutron Physics and the Meeting of Four Neutron
Centers in 1977.
The Meeting on Data on the Structure of the Atomic Nucleus and Radioactive Decay was also organized
by the Nuclear Data Section of the IAEA and took place in Vienna from May 3 to 7, 1976. The meeting was at-
tended by representatives of Austria, Belgium, the Federal German Republic, Gt. Britain, Holland, Hungary,
Italy, Japan, Poland, Rumania, the USA, the USSR, and Sweden. Some of the subjects brought up for discussion
were: definition of systems of exchange of nuclear data (bibliographical, numerical, and evaluated) and the
format of the exchange, the general rules and terminology (dictionaries, methods of evaluation), the interna-
tional file of evaluated data on the structure of the nucleus and decay (contents, structure, format, distribution),
and international cooperation on data compilation and evaluation.
In the USA the work on the evaluation and compilation of data on the structure of the atomic nucleus and
radioactive decay is concentrated in four laboratories (Brookhaven, Berkeley, Oak Ridge, and Idaho) and in the
University of Pennsylvania. Work will be done here on all mass chains, except A=21-44. That chain has been
traditionally the domain of the State University of Utrecht (Holland). The United States plans to make a revi-
sion of the A-chains once every four years and invites other countries to participate in this so as to make the
Translated from Atomnaya Energiya, Vol. 41, No. 6, p. 441, December, 1976.
This material is protected by copyright registered in the name of Plenum Publishing Corporation, 227 West 17th Street, New York, N.Y. 10011. No part
of this publication may be reproduced, stored in a retrieval system, or transmitted, in any form or by any means, electronic, mechanical, photocopying,
microfilming, recording or otherwise, without written permission of the publisher. A copy of this article is available from the publisher for $7.50.
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analysis easier for themselves, on the one hand, and, on the other hand, to make the data file international.
The US delegation reaffirmed the principle of free exchange of data of all forms.
Before the Vienna meeting, representatives of some West European countries got together to discuss
some questions of the compilation and evaluation of nuclear data (April 27, 1976, in Belgium). At their meeting
they pointed out the importance of international cooperation in the evaluation of nuclear data.
The Vienna meeting adopted as a recommendation the "Recent References" system of keywords as an
international system for the exchange of bibliography on data on nuclear structure and decay. The format of
the Oak Ridge laboratory was recommended as a provisional one for the exchange of numerical and evaluated
data.
The next meeting is planned for September or October, 1977. The site was not fixed definitely.
The proceedings of the meeting are in the Center of Data on Nuclear Structure and Nuclear Reactions
(Moscow).
IAEA SYMPOSIUM ON THE DESIGN
AND EQUIPMENT OF "HOT" LABORATORIES
B. I. Ryabov
Delegations from 32 countries and three international organizations participated in the Symposium which
was held Aug. 2-6, 1976, in Finland. A total of 46 papers were presented in four main sections: safety in
planning and design; systems of air transfer and purification; critically monitoring, fire protection, and waste
handling; radiation protection and administrative measures; operating experience. Primary attention was paid
to technical, structural, and organizational measures for increasing radiation safety during work with kilogram
quantities of plutonium and with gram quantities of transuranium elements. Interest in these problems has
been aroused by extension of fast reactor programs.
Increased radiation safety during work with irradiated fuel with a high plutonium content required addi-
tional safety measures. Comparatively few special laboratories are equipped for this purpose; mention was
made of only two new facilities being built in Japan and projects for another two in the USA. In other countries,
existing facilities are being reconstructed and modernized. Most laboratories for work with irradiated fuel in-
corporate large "hot" caves (up to 20 m long, 4-6 m wide, 7-10 m high) with a high degree of containment,
biological shielding for activities up to 106 Ci, dismountable cover, bridge crane inside, and electromechanical
manipulators. Besides large hot caves, ordinary-sized ones are used, but with dismountable shielding (or re-
tractable wall) and boxes. Caves and boxes are equipped with critical-mass safety devices, a system for
handling the product without affecting the air-tightness, an efficient system for decontaminating the exhaust air,
and automatic fire-fighting installations employing liquid carbon dioxide or tetrafluorodibromomethane. Par-
ticular attention is paid to fire safety because the products are pyrophoric, which means that the possibility of
a fire breaking out cannot be ruled out, and in such an event the filters go out of service and the ejection of a
large quantity of activity is unavoidable.
In the United States the mean radiation dose allowed for personnel in "hot" laboratories is 1 rem/yr
(0.5 mrem/h), the buildings and equipment are designed to withstand hurricane winds (tornadoes) and seismic
activity of up to 9 points, which makes the construction about 10% more expensive but guarantees that dangerous
contaminants are not dispersed in the event of natural disasters. When new laboratories are designed and old
ones rebuilt, measures are planned for the well-timed shutdown of plants when breakdowns occur, and for the
deactivation, dismantling, and evacuation of the equipment.
Much consideration is given to the standardization of the basic equipment and its subassemblies; this is
a means not only of cutting the cost of radiation safety but also of increasing it since this makes it possible to
Translated from Atomnaya Energiya, Vol. 41, No. 6, pp. 442-443, December, 1976.
This material is protected by copyright registered in the name of Plenum Publishing Corporation, 227 West 17th Street, New York, N.Y. 10011. No part
of this publication may be reproduced, stored in a retrieval system, or transmitted, in any form or by any means, electronic, mechanical, photocopying,
microfilming, recording or otherwise, without written permission of the publisher. A copy of this article is available from the publisher for $7.50.
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introduce into practice equipment that is well designed, tried and tested, and therefore reliable. This purpose
is also served by the use of high-quality materials. Standardized equipment and subassemblies is manufactured
on an industrial scale in France and is sold not only on the home market. Another aspect of increased safety
is that of automation of frequently recurring operations, such as analysis of fuel composition, 7 spectrometry,
and photometry. The operations are carried out using a computer. To automate auxiliary operations, France
has developed a new manipulator, the MM-8, with programmed control and feedback, the program being re-
corded in the computer automatically when the operator makes the required movements manually. A short-
coming of the manipulator is that all the slave motors are inside the cave and this cannot ensure a long period
of operation with a high level of 7-ray activity. The air from the a- and y-contaminated drive mechanisms,
shielded by a sheath with forced air, is expelled through a filter.
Stringent requirements are put on the ventilation systems of hot laboratories. Caves and boxes are kept
at a vacuum of 25 to 40 mm H20 (or even more) and the pressure drop between a cave and the repair zone is
6-25 mm H20. Most caves and boxes have a vent system for inflow ventilation which maintains the specified
parameters of air interchange if the vacuum drops because of a leak (rupture of a glove, broken glass, etc.);
in this case an alarm system is actuated and a sound signal is sounded. The inflowing air is purified by filters,
and the exhaust from hot caves and boxes is, as a rule, in many stages. 131I is trapped with high-quality carbon
filters, designed with a frame compressed by a screw mechanism which ensures uniform density of the pow-
dered carbon. A sophisticated air purification system is used when fuel elements are taken apart. Behind the
carbon filters are scrubbing columns which are irrigated with sulfate compounds, mercury nitrates, and other
solutions. After purification, the air is treated on filters of diodide or silver nitrate and on a monitoring filter.
The coefficient of air purification with such a system is 105. It was particularly noted that there are as yet no
filters resistant to high temperature (more than 200?C); consequently, in a fire the purification systems cease
to function.
Major accidents can be caused by violation of the critical-mass safety. Data were presented at the sym-
posium about the force of the bang in a box during a spontaneous reaction in terms of exploding TNT: with
2.1017 fissions per second the force of the bang is that of 25 g TNT, and at 7. 1018 fissions/sec, 1000 g TNT.
The most likely minimum accident is with 2 1017 fissions/sec, but even in this case boxes are destroyed. A
possible accident is prevented by critical-mass-safety devices as well as the limitation of the quantity of plu-
tonium in the apparatuses. Particular difficulty is presented by the monitoring of critical-mass safety. Under
development are new two-stage scintillation detectors which begin operating at the beginning of the reaction and
give an alarm signal at a dose of 0.6 R/sec.
Organizational and technical measures enabling safe operating conditions to be maintained in "hot" labo-
ratories found an important place in the discussion. This includes the development of new sanitary regulations,
detailed reports by existing enterprises on the safety measures in plants, on a concrete radiation facility, sta-
tistics, etc. After considering and approving these reports, the competent state organs give permission to con-
tinue operations. Reports are resubmitted if the technology at the plant is altered or if the basic equipment is
changed (France). In many countries, permission for work with plutonium is renewed each year with an indica-
tion of the maximum quantity allowed the given laboratory. The personnel undergoes the requisite training and
should have high qualifications, and the basic equipment is subjected to a prophylactic examination and main-
tenance at least every 18 months.
Considerable interest was aroused among foreign delegations by the USSR delegation report which pre-
sented the main directions taken in solving the safety problems in designing "hot" laboratories and experimen-
tal facilities in our country. The symposium proceedings will be published by the IAEA.
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SECOND SEMINAR ON COMPUTER SIMULATION
OF RADIATION AND OTHER DEFECTS
Yu. V. Trushin
The seminar, which was held in the M. I. Kalinin Polytechnic Institute in Leningrad, June 22-24, 1976,
was devoted primarily to radiation defects. The seminar was opened with a review by A. N. Orlov (A. F. Ioffe
Physicoteclmical Institute, Academy of Sciences of the USSR) who analyzed publications on "Radiation effects
and the nuclear power industry" in the light of requirements put upon the material of thermonuclear reactor
walls. Computer simulation can be used to solve some problems and in individual cases is as yet the only ac-
cessible method of investigation.
A paper by V. Ya. Migalena (Physicotechnical Institute of the Academy of Sciences of the USSR, Kharkov),
based on the results of original papers by research teams, presented methods of calculating the spectra of
primary knock-on atoms (PKA), taking account of elastic and inelastic nuclear processes during the scattering
of nucleons of intermediate energy (up to 50 MeV). At this energy there is a significant anisotropy during
scattering of primary particles and, consequently, an attendant anisotropy in the spatial distribution of the
PKAs. A set of programs has been created for calculating the energy and spatial characteristics of PKAs
during the interaction of protons, neutrons, and heavy ions with an energy of the order of 1 MeV/nucleon with
different materials. The elastic scattering cross sections are determined from the optical model; inelastic
processes at energies exceeding 10 MeV are described within the framework of the exciton model, taking ac-
count of the contribution of the pre-equilibrium and equilibrium components in the nuclear decay. In the inter-
action of heavy ions, allowance is made for the nuclear charge being screened by electrons. Calculated results
were given for spectra of PKAs from protons with an energy of 5-25 MeV and heavy ions for some structural
materials. In the case of light elements with A < 40, when elastic nuclear scattering is included the total num-
ber of PKA.s is increased by a factor of 5-10 in comparison with calculations without account for nuclear in-
teractions. Consideration is being given to the possibility of using protons and heavy ions to simulate radiation
damage from fast and superfast neutrons.
A paper by V. V. Ogorodnik (Institute of Problems of Materials Science, the Academy of Sciences of the
Ukrainian SSR) was devoted to computer simulation of radiation defects by the Vineyard method for binary crys-
tals. The investigations are carried out on the model of the TIC crystal which has NaC1 structure. Morse po-
tential was used as the interaction potential. The equilibrium configuration was calculated for an ideal crystal
of 125 atoms in the free state (without imposing boundary conditions at the surface). Practically uniform com-
pression of the crystal was achieved under the action of surface tension forces and it amounted to 4%. Similar
calculations were carried out for crystals with specified defects (vacancies in metal and carbon sublattices,
metal and carbon interstitials). The energy released when a vacancy moves from a center to the surface is
2.4 eV, which in this model can be assumed to be the formation energy of a metal vacancy. Significant dis-
placements in the direction of the vacancies were experienced by nearest-neighbor carbon atoms (up to 0.25
lattice constant). The interstitial atoms take up a dumbbell position in the (111) direction.
In his paper, Yu. R. Kevorkyan (I. V. Kurchatov Institute of Atomic Energy) gave the results of work done
by a group of researchers on the simulation of cascades of atomic collisions in a-Fe with allowance for inelastic
losses, the interactions of moving atoms with defects formed earlier in the cascade, and annealing for 104 sec
at 300 and 800?K. The displacement efficiency decreases with the PICA energy down to 15 keV. More than 70%
of the vacancies are combined into complexes and more than 80% of the interstitials are individual. The an-
nealing at 300?K recombines 90% of the defect pairs, and this rises to 80% at 800?K. Distributions of vacancy
clusters were also obtained according to size before and after annealing and some other cascade characteris-
tics.
Translated from Atomnaya Energiya, Vol. 41, No. 6, pp. 443-444, December, 1976.
This material is protected by copyright registered in the name of Plenum Publishing Corporation, 227 West 17th Street, New York, N.Y. 10011. No part
of this publication may be reproduced, stored in a retrieval system, or transmitted, in any form or by any means, electronic, mechanical, photocopying,
microfilming, recording or otherwise, without written permission of the publisher. A copy of this article is available from the publisher for $7.50.
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L. K. Kuznetsov (N. I. Lobachevskii State University, Gorki) discussed the simulation of different pro-
cesses occurring in bee metals (a-Fe, Mo, W). As a result of the calculation of cascades of displacements, it
was found that (contrary to Billerls conclusions) their spatial configuration depends on the direction of dis-
placement of the PKAs. The most stable planar clusters of vacancies are those lying in the (110) plane and
having the maximum number of bonds of the (111) type, while the bulk clusters are complexes of octahedral
form. The formation energy of a planar complex is proportional to the number of vacancies N in the complex,
and that of bulk complexes is NO. The motion of dislocations in a field of randomly distributed obstacles (in
the Foreman? Mackean approximation) is due to kinks in dislocation segments. As the stress increases it be-
comes possible for segments to be stripped from the obstacles. At high stresses disolcations may advance be-
cause of bowing of unstable segments. Two models of swelling have been developed on the basis of the diffusion
mechanism of pore growth. Helium atoms produced in (n, a) reactions are the pore nuclei. Calculations for
stainless steel 304 yielded data about the size distribution of pores and about swelling and also made it pos-
sible to evaluate the effect of irradiation conditions on these parameters.
V. V. Kolomytkin (I. V. Kurchatov Institute of Atomic Energy) presented a paper on the simulation of
certain mechanisms of radiation creep in the initial stage of reactor irradiation when depleted zones are the
most significant obstacles to dislocations. Radiation strengthening of platinum was simulated by taking account
of the experimental data, particularly those obtained with an ion projector. Assuming that the surface of the
depleted zone, growing during intersection with a dislocation zone, is characterized by a surface energy of'
and that the displacement stress obtained by calculation according to the Foreman?Mackean model is equal to
the stress necessary to increase the zone surface, the authors obtained y =240 ergs/cm2. Two simultaneously
operating mechanisms of radiation creep were considered; 1) pinning of glissile edge dislocations by depleted
zones; and 2) irradiation-accelerated climbing of dislocations. The inhomogeneity of the long-range disloca-
tion fields is taken into account. The results are equal to experiments for a-Zr.
In their paper, S. I. Zaitsev and E. M. Nadporny (Institute of Solid State Physics, Academy of Sciences of
the USSR) presented the results of simulating the motion of dislocations through point radiation defects and
other defects. Studies have been made of the problem of dislocation motion in a plane with randomly distributed
immobile obstacles possessing an intrinsic elastic field typical of impurity and radiation defects. An obstacle
is simulated by a barrier with Fleischer?Gibbs type of potential with a critical bending angle of 150?. The
motion of dislocation is considered as a consequence of instantaneous displacement from one equilibrium posi-
tion to another after a waiting time. The activation site and the waiting time are found by the Monte Carlo
method. The dislocation velocity is found as a function of the stress, temperature, and barrier heights, and the
activation energy as a function of the stress. Calculations were carried out for 103 to 104 obstacles for dif-
ferent forms of area. It was shown that the activation process proceeds in correlated fashion through ',weak"
angles, and the onset and propagation of quasikinks are important for dislocation motions. At a low tempera-
ture and low stress the velocity of a dislocation depends on its length but with more than 100 obstacles per dis-
location this dependence vanishes.
In addition to the papers enumerated, the seminar heard eight brief communications on computer simula-
tion of dislocations, dislocation pile-ups, phase boundaries, and microcracks in solids. The seminar was at-
tended by 75 representatives of 21 scientific institutions from ten cities of the USSR.
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INTERNATIONAL CONFERENCE
ON "ION-EXCHANGE THEORY AND PRACTICE"
V. V. Yakshin
The conference, which was held July 25-30, 1976, in Cambridge, England, was attended by 250 specialists
from 26 countries. The considerable advances made in the practical application of ion-exchange processes
since the previous conference in 1969 made it necessary to hold this meeting of scientists for an exchange of
views.
The conference heard and discussed 41 papers in five principal areas: development of the synthesis of
ion-exchange resins (7 papers), ion-exchange equilibrium and kinetics (10), water treatment and purification
(10), processes of separation of organic and inorganic materials (5), and the hydrometallurgy of nonferrous,
rare-earth, and radioactive elements (9). Thus the main attention was given to investigations on the equilib-
rium and kinetics of ion exchange, the use of ion-exchange resins in water treatment processes and waste
processing, as well as in the hydrometallurgical industry.
Of the papers on the development of the synthesis of ion-exchange resins and the influence of their struc-
ture on reactivity, the following should be singled out: "The mechanism of the formation of a polymer network
in styrene-divinyl benzol copolymers" (L. Rubinsk and D. Smith, Gt. Britain) and "The effect of resin structure
on the mechanical strength of its grains" (L. Gollan and D. Irving, Gt. Britain). The first paper considered the
mechanism of formation of a macromolecular skeleton during copolymerization of styrene with commercial
divinyl benzol. It was established that in the process of copolymerization of these components there is tangling
of chains and nonuniform distribution of side chains. The first polymerization products are enriched in divinyl
benzol (compared with the average content of the initial components). However, the nonuniformity of the co-
polymer structure is obliterated by the tangling and interpenetration of the styrene and divinyl benzol chains.
As a result, an extremely compact structure of ion-exchange resins is obtained.
The second paper compared the mechanical properties of ion-exchange resins obtained on the basis of the
copolymers of styrene and acrylonitrile with divinyl benzol. It was found that the character and water content
of the ion-exchange resin prove to significantly affect the mechanical strength and that helium ion-exchange resins
based on styrene and divinyl benzol copolymers are harder than acryl-based resins and therefore split more
readily. Macroporous structures are more stable in the osmosis respect, but deform more easily than the
helium type. This should be taken into account when choosing the type of resin for practical application.
In the paper "Oxidation disintegration of ion-exchange resins and its prevention," the American special-
ist L. Goldring presented the results of studying the stability of cation-exchange resins of the sulfostyrene
type, disintegrating under the action of hydrogen peroxide and oxygen in the presence of metal ions. Iron and
copper prove to be the strongest catalysts of the process of oxidation disintegration of ion-exchange resins. In
order to inhibit them, iron and copper are converted into inert complex compounds by the introduction of deriv-
atives of ethylene-diaminotetraacetic acids.
Of the papers on ion-exchange equilibrium and kinetics, those devoted to the study of ion-exchange processes,
complicated by complexing in the resin phase and in the solution, and those devoted to the study of multicom-
ponent mixtures on model solutions may be cited as examples. Mention can be made of the communication "The ki-
netics of the reaction of the propagating layer in ion-exchange resins" (G. Schmukler et al., Israel) where the exam-
ple of the absorption of hydrogen ions by the sodium form of carboxylsilicate cation-exchange resin is used to con-
sider a model according to which the ion-exchange rate is determined by the velocity of propagation of the
saturated layer into the ion-exchange grain. The paper "Investigating slowly diffused particles in ion-exchange
resins" (K. Behu et al., Gt. Britain) presented the results of investigations on the kinetics of plutonium (IV) ab-
sorption from nitrate solutions on the vinylpyridine ion-exchange resin Ionac XAX 1284.
Translated from Atomnaya Energiya, Vol. 41, No. 6, pp. 444-445, December, 1976.
This material is protected by copyright registered in the name of Plenum Publishing Corporation, 227 West 17th Street, New York, N.Y. 10011. No part
of this publication may be reproduced, stored in a retrieval system, or transmitted, in any form or by any means, electronic, mechanical, photocopying,
microfilming, recording or otherwise, without written permission of the publisher. A copy of this article is available from the publisher for $7.50.
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The use of ion exchange to recover uranium was the subject of a paper (H. Gardner and R. Coonin, Gt.
Britain) which considered the possibility of transition from strong-base anion-exchange resins to the weak-
base resin Amberlite XE 229. Notwithstanding the lower capacity for uranium (by 15%), the weakly alkaline
anion-exchange resin is more selective and desorbs uranium more readily, thus ensuring that high-quality
uranium dioxide is obtained. A successful 4-yr trial operation of a technological flowsheet employing the weak-
base anion-exchange resin Amberlite XE 229 confirms the conclusion made by the authors. The use of weak-
base anion-exchange resins in the uranium industry was also the subject of the paper by D. Naden and G. Willie
(Gt. Britain). On the basis of laboratory experiments and the results of pilot plant operation, the authors came
to the conclusion that macroporous anion-exchange resins can be used effectively in apparatus with a liquefied
sorbent layer, especially in obtaining high-purity uranium. Further improvement of the apparatus for ion-ex-
change was considered in a paper by A. Himsley and E. Farkas (Canada). A distinctive feature of anion-ex-
change equipment is the use of a plate-type contactor in the sorption operation; with an initial concentration of
1 g/liter uranium in the solution this enables the resin to be saturated to 78 enter with a discharge of less
than 1 mg/liter into the filtrate and an eluate concentration of 35 g/liter uranium.
Two papers pointed to the feasibility of the practical application of ion-exchange processes for extrac-
tion and purification of relatively inexpensive nonferrous metals such as copper and nickel. The data of these
papers confirm the promise held out by the ion-exchange technology in nonferrous metallurgy.
A feature of the conference were papers on a new area of ion-exchange technology, the use of impreg-
nated polymer materials to separate organic and inorganic compounds. These materials are obtained by intro-
ducing liquid complexing agents (extractants) into the resin structure when the polymer matrix is formed or by
impregnating the ready polymer base with extractant. A paper by H. Kaukzor and A. Meier (Federal Republic
of Germany) described the physicochemical properties of impregnated macroporous styrene-divinyl-benzol
copolymers (Levextrel) with tributyl phosphate (TBP) and di-(2-ethyl-hexyl)-phosphoric acid (D2EHPA) and
considered the possibility of their being used to recover uranium and plutonium, to separate trace quantities
of chromium and indium from concentrated solutions of heavy metals, to separate heavy lanthanides, and to
purify them from radioactive contaminants. Levextrel TBP resin was successfully tested under pilot plant con-
ditions. In the opinion of the authors, resins of this type combine the advantage of extractants and sorbents and
can be used to extract metals from dense pulps or dilute solutions from the underground leaching of various
ores. Other papers on this subject included "Hydrometallurgical applications of resins impregnated with hy-
droxyomine, hydroxyquinoline, and hydroxamic acid" (F. Vernon, and Ch. Aisles, France) and "Further devel-
opment of metal extraction with impregnated resins" (A. Warszawski and A. Paczornik, Israel) which discuss
various liquid complexing agents and polymer matrices for obtaining impregnated resins and possible ways of
using them in hydrometallurgical processes.
The conference devoted considerable attention to ion-exchange treatment of water to remove contaminants
of an organic and inorganic nature as well as processes of demineralization in the preparation of water for
boilers and high-pressure turbines. At the present time ion-exchange technology has some indisputable advan-
tages over other technological processes, as was convincingly demonstrated by the conference delegates with
practical examples.
Among the papers on the application of ion-exchange resins to separate compounds, a communication of
unquestionable interest was "Ion-chromatography, principles and applications" (H. Small and D. Salk, USA)
which described a new analytic method for the analysis of anions and cations in solutions, a method which is
based on ion-exchange principles and employs a solution-conductivity sensor as a detector. At the present
time the USA has started manufacture of ion chromatographs which made for easy analysis in solutions of ions
of alkali-earth metals, primary, secondary, and tertiary amines and ammonium bases, anions of halides, ni-
trates, nitrites, iodates, and others, with a sensitivity of 10-8.
The work of the conference showed that ion-exchange processes all find great practical application in the
most diverse areas of science and technology such as hydrometallurgy, protection of the environment, analytic
chemistry, the atomic industry, water treatment, and separation and purification of organic and inorganic com-
pounds. Further progress in these areas is bound up with the development of new ion-exchange resins, the con-
struction of-efficient ion-exchange equipment, and the development of efficient technological processes employ-
ing new ion-exchange materials and equipment.
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BOOK REVIEWS
A. M. Petroslyants
FROM THE SCIENTIFIC QUEST TO THE ATOMIC
INDUSTRY. CONTEMPORARY PROBLEMS OF
ATOMIC SCIENCE AND ENGINEERING IN THE
USSR*
Reviewed by Yu. I. Koryakin
The fact that the book under review has had three editions within a relatively short time (first edition in
1970, second in 1972) attests to the unflagging interest in it. The "publishing viability" of any scientific book
is determined by a number of factors, two of which are perhaps the principal ones: the timeliness of the sub-
ject and the author's skill in presenting the material. This book boasts both qualities, and with each edition
they have undergone a welcome evolution.
The timeliness of the subject is obvious and is growing continuously and rapidly. Atomic science and
engineering of our country have now become one of its major productive forces and considerable intellectual
and material resources of the national economy are already involved in this area and are continuing to become
involved on an increasing scale with each year. It is precisely in the use of atomic energy that hopes lie
for the solution of serious diverse problems of power engineering and technology which, as is known, provide
the means for the functioning of the entire national economy.
In recent years, especially in the period covered by the three editions of the book, there has been an
enormous qualitative and quantitative growth in the application of atomic energy in our country and elsewhere,
and this has been reflected in part in the successive printings.
In speaking of the author's skill, one can scarcely fail to note that in his preface to the first edition he
called the material of the book 'sketches of the history of atomic science and engineering.' But this is only one
aspect of the style of the presentation. In the first place, to a significant degree the book stems from the au-
thor's extensive experience in the utilization of atomic energy (almost from the very beginning) and his knowl-
edge. In the second place, it is more characteristic than previous publications when, naturally, the author
wanted above all to share his personal observations and recollections with the reader. But as the range of ap-
plication of atomic energy in the USSR grew, so did the store of scientific and technical information which the
author had and which he wanted to, and indeed had to, take along with him on his "route of publication." And
since it is impossible to put everything in a book, the sketch genre faded into the background in successive
editions. The retrospective view proved to be subordinate to the view of the present state and the future ap-
plications of atomic energy, especially as the very title of the book called for (if not required) precisely such
accentuation.
This does not, of course, lead to a question about which approach is preferred: the author has a suf-
ficient mastery of both the methods of science journalism and the subject presented, which is equally important.
Nevertheless, it seems that the contents of the latest edition corresponds to the title to a greater extent than
the previous editions.
And here we must emphasize that the title "Contemporary Problems...," as in fact follows from the con-
tents of the book, should not be taken literally. Consideration of problems taken to mean tasks, goals, endeav-
ors, or hopes in the domain of the utilization atomic energy, is naturally given due attention. But, as a rule,
this follows from the detailed description of the present state of the art or the level reached in scientific and
technical development and the scale on which the areas of application of atomic energy have been introduced
into the practice of the national economy. Usually these areas are called problems.
*Atomizdat, Moscow (1976).
Translated from Atomnaya Energiya, Vol. 41, No. 6, pp. 446-447, December, 1976.
This material is protected by copyright registered in the name of Plenum Publishing Corporation, 227 West 17th Street, New York, N.Y. 10011. No part
of this publication may be reproduced, stored in a retrieval system, or transmitted, in any form or by any means, electronic, mechanical, photocopying,
microfilming, recording or otherwise, without written permission of the publisher. A copy of this article is available from the publisher for $7.50.
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The range of problems (in the sense indicated above) elucidated by the author is wide: from fundamental
research to what has become ordinary practice. An enumeration would take too much space, and the "assort-
ment" of these areas has already begun to be canonized to a certain degree, especially since the author ad-
dresses his book in the main to the wide reading public. And in such a case the author is fully justified in
wanting to give the reader only high-quality, verified material, and to avoid turning the book into a receptacle
of unverified ideas and assumptions as if they were not enticing and logically founded. The author Is reputa-
tion prompts necessary discretion with respect to this.
But one danger lurks in such a position by the author. The point is that in describing the areas of appli-
cation which have developed and especially the research on atomic energy, it is easy to become categorical and
to be tempted to "cross the t's and dot the i's." Yet it is known that in science and technology there are un-
expected reversals, unforeseen courses of events, and even dead ends. Atomic science and technology are not
an exception. And although the author in the main avoided the temptations to be categorical, this is true only
in the main since there are some shortcomings in this respect. Speaking of shortcomings, mention should be
made, e.g., of cases where the author converses with the reader as if in passing (although the topic requires
detailed discussion), but these cases are rare. The shortcomings mentioned should, of course, be regarded as
unavoidable in the author's advance and his amazing creative activity and operativeness. In respect of the lat-
ter, it is a very good thing, for example, that the edition under review already has information about the use of
atomic energy that was reflected in the materials of the 25th Congress of the Communist Party of the Soviet
Union. To be sure, the author must share the merit of operativeness with Atomizdat which, incidentally, saw
to it that the book was well designed.
V. A. Zuev and V. I. Lomov
PLUTONIUM HEXAFLUORIDE*
Reviewed by N. P. Galkin
In the past two decades considerable progress has been made in the chemistry and technology of pluto-
nium hexafluoride, especially in connection with the development of fluoride methods of regenerating irradiated
uranium-plutonium oxide nuclear fuel. Consequently, the publication of this monograph is fully justified.
The monograph systematizes the disconnected information in the literature about methods of obtaining
plutonium hexafluoride and its properties, published up to 1973. The monograph consists of six chapters. The
introduction describes the history of the discovery of plutonium hexafluoride as well as some of its peculiar-
ities as compared with other known hexafluorides; particular note is taken of the high reactivity of this com-
pound as well as its thermal and radiation instability.
Chapter I presents laboratory methods of obtaining and purifying plutonium hexafluoride, going into a
detailed consideration of the kinetics and mechanism of interaction of the various plutonium compounds with
fluorine and halogen fluorides (CIF, C1F3, BrF3, and BrF3). The rules for storing and handling plutonium
hexafluoride are given.
Chapter II is devoted to the physical properties of plutonium hexafluoride. It gives the most reliable
data on the melting point, boiling point, vapor pressure, and triple point of this compound. The known thermo-
dynamic, optical, magnetic, mechanical, and other properties of plutonium hexafluoride are described.
The most interesting chapter, Chapter III, brings together all the known chemical properties of plutonium
hexafluoride. The reactions of the hydrolysis of water, and interactions with reducing agents, metal fluorides,
and structural materials are considered. The material of Chapters II and III makes it possible to predict the
behavior of plutonium at various stages in the process of regeneration of irradiated uranium-plutonium nuclear
fuel by fluoride methods.
*Atoxnizdat, Moscow (1975).
Translated from Atomnaya Energiya., Vol. 41, No. 6, p. 447, December, 1976.
This material is protected by copyright registered in the name of Plenum Publishing Corporation, 227 West 17th Street, New York, N.Y. 10011. No part
of this publication may be reproduced, stored in a retrieval system, or transmitted, in any form or by any means, electronic, mechanical, photocopying,
microfilming, recording or otherwise, without written permission of the publisher. A copy of this article is available from the publisher for $7.50.
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Chapters IV and V are devoted to the thermal and radiation instability of plutonium hexafluoride. These
characteristics have a significant effect on the apparatus design of fluoride methods of fuel regeneration and
should be taken into account when designing equipment.
Chapter VI sums up the results of research on the physical and chemical properties of plutonium hexa-
fluoride from the point of view of their possible use in the technology for obtaining and purifying plutonium
hexafluoride during processing of irradiated oxide nuclear fuel.
Fluoride methods of regenerating irradiated fuel elements are not yet in practical use. Therefore, the
authors of the book confine themselves to describing the promising directions in this domain. They discuss
problems of plutonium extraction from irradiated fuel and possible means of purifying it from fission products.
Difficulty has been noted in purifying plutonium hexafluoride from ruthenium fluoride.
On the whole, the book under review quite fully reflects the state of research in the domain of the chem-
istry and technology of plutonium hexafluoride. It is based on the use of contemporary phycicochemical data.
Among the virtues of the book is the fact that the authors link up the thermal investigations on the physical and
chemical properties of plutonium hexafluoride with the possibility of their practical application in the proces-
sing of irradiated fuel.
Unfortunately, the book contains typographical errors and stylistic errors. Regardless of the short-
comings mentioned, the book is of great interest and can undoubtedly be recommended to engineering and
scientific workers who specialize in the chemistry and technology of the fluorides of actinides.
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INDEX
SOVIET ATOMIC ENERGY
Volumes 40-41, 1976
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AUTHOR INDEX
Abolmasov, Yu. P. 845
Abramov, B. D. - 822
Afanasiev, V. A. - 907
Afrikanov, I. N. - 468, 585, 955,
1055
Agapova, N. P. - 468, 585, 955,
1055
Ageenkov, A. T. - 243, 627,
755
Akap'ev, G. N. - 251
Aleinikov, V. E. - 975
Aleksdkhin, R. M. - 235, 428
Aleksandrov, B. M. - 1072
Aleksandrov, M. L. - 740
Alekseev, V. A. - 85
Alekseev, Yu. V. - 336
Alekseeva, S. A. - 513
Alferov, A. V. - 1067
Alikaev, V. V. - 1026
Amaev, A. D. - 778
Anan'ev, E. P. - 1
Anan'in, V. M. - 304
Andreev, B. M. - 516
Andreev, L. G. - 407, 1001
Antipin, N. I. - 291
Antipina, M. M. - 14
Arifmetchikov, E. F. - 101,
679, 862
Aripov, M. M. - 997
Artamonov, V. S. - 368, 373
Artemov, A. I. - 770
Ashkinadze, G. Sh. - 663
Asvrin, V. I. - 853
Azarenko, A. V. - 820
Azimov, S. A. - 423
Babadzhanyants, N. V. - 1072
Babykin, V. V. - 993
Badanin, V. I. - 838, 1080
Bagdasarov, R. E. - 871
Bagdasarov, Yu. E. - 612, 682
Baibakov, V. D. - 914
Baikulov, V. A. - 573
Balakin, I. M. - 558
SOVIET ATOMIC ENERGY
Volumes 40-41, 1976
(A translation of Atomnaya Energiya)
Balankin, S. A. - 909
Balashov, A. P. - 591
Balbekov, V. I. - 1061
Balukova, V. D. - 765
Bamburov, Yu. G. - 378
Baranov, I. A. - 1072
Baranov, S. A. - 987
Baranov, V. M. - 37
Baranov, V. Yu. - 110
Barashenkov, V. S. - 251
Bartolomei, G. G. - 914
- Baturov, B. B. - 320
Batusov, Yu. A. - 1030
Batyrbekov, G. A. - 462
Bazavov, D. A. - 94
Beda, A. G. - 425
Beketov, A. R. - 572
Belcmukhambetov, E. S. 462
Belanova, T. S. - 368, 373
Belokopytov, V. S. - 1058
Belov, A. F. - 675
Belova, L. N. - 204
Berdov, B. A. - 930
Berzhatyi, V. I. - 462
Bessonov, V. A. - 477
Beznosikova, A. V. - 594
Bibilashvili, Yu. K. - 14, 37
Biryukov, V. A. - 671
Birzhevoi, G. A. - 356
Blanovskii, A. I. - 89
Blinkov, D. I. - 917
Bochek, G. L. - 421
Bogolyubov, N. N. - 318
Bogoyavlenskii, V. L. - 1058
Boiko, V. I. - 261, 1014
Bol'shakov, 0. P. - 996
Bondarenko, V. V. - 871
Bondarev, V. D. - 967
Borisov, B. R. - 558
Borisov, E. A. - 477
Borisova, S. I. - 571
Borkovskii, M. Ya. - 284
Borman, V. D. - 78
Borshchev, V. P. - 147
Briskman, B. A. - 967
Brovin, M. M. - 342
Browne, J. S. - 587
Bubnov, V. K. - 738
Budker, G. I. - 50, 256
Buldd, S. M. - 423
Buksha, Yu. K. - 612
Bulanenko, V. I. - 1003
Buntushkin, V. P. - 511
Buravtsov, A. A. - 243, 627
Burykin, A. A. - 738, 744
Bushuev, A. A. - 342
Bushuev, A. V. - 465, 793,
1037
Bute, V. V. - 503
Butra, F. P. - 650, 955
Bykov, V. N. - 356, 360, 802
Bykovskii, V. S. - 1006
Chakhlov, V. L. - 1066
Chebotarev, N. T. - 594
Chechetkin, Yu. V. - 1095
Cherednichenko-Alchevskii,
M. V. -297
Chernetsov, 0. K. - 605
Chernov, I. P. - 661
Chernova, T. A. - 826
Chernukhin, Yu. I. - 647
Chernyshevich, V. P. - 407
Chesnokova, V. D. - 94
Chetverikov, A. P. - 66, 1008
Chikul, Yu. I. - 210, 927
Chistov, E. E. - 897
Chudinov, V. G. - 912
Chuev, V. I. - 955
Chuzhinov, V. A. - 563, 842
Dashkovskii, A. I. - 297, 468,
585
Degtyarev, V. A. - 185
Dekalova, A. N. - 364
Denisov, V. G. - 617
Denisov, V. P. - 326
Derbenev, Ya. S. - 50
Desyatov, V. M. - 555
Didenko, A. N. - 104
Dikanskii, N. S. - 50
Dindun, A. S. - 503
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Declassified and Approved
Dmitriev, P. P. - 75, 657,
1091
Dmitriev, V. D. - 360, 802
Dmitrieva, Z. P. - 75, 1094
Dod', A. I. - 509
Dolgov, A. D. - 856
Dolgov, V. V. - 687
Dolgova, K. A. - 558
Dolgushin, V. M. - 378
Dolinin, V. A. - 237, 848
Dollezhal', N. A. - 137, 154
Donichkin, A. G. - 972
Doroshenko, G. G. - 550
Dubinin, V. N. - 1085
Dubinskii, V. E. - 251
Dubovskii, B. G. - 283, 871,
1001
Dalin, V. A. - 405, 457
Duvanov, V. M. - 465, 793
Dymkov, Yu. M. - 605
Dyvydov, E. F. - 14
Dzhandzhgaba, B. Sh. - 842
Efeshin, A. N. - 871
Efimov, V. N. - 907
Efremov, E. A. - 711
Efrimov, A. V. - 1032
Egiazarov, M. B. - 147, 1037
Eismont, V. P. - 972
Elovsldi, 0. A. - 500
El'tsov, A. I. - 1076
Emellyanov, I. Ya. - 137, 147,
693, 939
Entinzon, I. R. - 59
Ermatov, S. E. - 462
Ermolaev, M. I. - 1073
Ershov, V. M. - 579
Ershova, Z. V. - 243, 627
Evdokimov, 0. B. - 924
Evstigneev, V. V. - 261, 1014
Ezhov, V. K. - 711
Faddeev, M. A. - 1089
Fedorov, V. A. - 995
Fedorova, A. F. - 94
Fedotkin, A. S. - 757
Fedyaev, S. K. - 299, 301
Fedyakin, R. E. - 907
Filipchuk, E. V. - 693, 830
Filippov, A. G. - 693
Filippov, E. M. - 208, 788, 864,
935, 936, 937
Filippov, V. N. -778
Filyushkin, I. V. - 267
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Fisenko, V. V. - 1067
Flerov, G. N. - 251
Fomushkin, E. F. - 202, 1083
Frolov, V. V. - 1003, 1051
Frolova, G. A. - 550
Gabeskiriya, V. Ya. - 66, 1008
Gaidamachenko, G. S. - 820
Galkin, N. P. - 1109
Ganev, I. Kh. - 323
Gaponov, V. A. 256, 342
Gavar, V. V. - 503
Gavrilov, V. D. - 808
Gavrilov, V. V. - 1083
Geller, B. E. - 638
Gerasimov, A. S. - 1009
Gerasimov, V. V. - 617
Gerasimov, Yu. A. - 529
Gerasimova, V. V. - 40
Gerchikov, F. L. - 581, 645,
1068
Gerdt, V. P. - 975
Gertsev, K. F. - 1061
Gimel'shtein, E. G. - 995
Ginkin, V. P. - 62
Gladkov, V. P. - 304, 306, 519
Glazkov, 0. M. - 320
Gnidak, N. L. - 89
Gochaliev, G. Z. - 571
Gofen, G. I. - 905
Gol'din, M. L. - 525
Golikov, I. V. - 955
Golodnyi, Yu. F. - 60
Golovachev, M. G. - 1078
Golovnin, I. S. - 14, 26, 37, 91
Golubev, L. I. - 243, 247, 627,
821
Goncharov, V. A. - 808
Gorbachev, B. I. - 94
Gorbachev, E. A. - 261, 1014
Gorbatov, N. E. - 1042
Gordeev, V. V. - 725
Gordienko, P. S. - 511
Gordina, V. M. - 851
Gorobtsov, L. I. - 247, 821
Goryunova, V. S. - 950
Goshchitskii, B. N. - 912
Gramenitskii, I. M. - 1032
Grigor'ev, E. I. - 308
Grinevich, N. A. - 477
Grishaev, I. A. - 421
Grishchenko, A. I. - 342
Gromova, A. I. - 617
Gryazev, V. M. - 14
Gryzina, V. V. - 1008
Gurin, V. N. - 283
Gurov, A. D. - 301
Gusev, A. A. - 641
Gusev, N. G. - 863, 890
Gusev, 0. A. - 334
Gusev, V. M. - 1055
Guseva, T. M. - 513
Gushchin, V. V. - 185
Gutnikova, E. K. - 202
Houve, R. E. - 587
lbragimov, M. Kh. - 117
thragimov, Sh. Sh. - 462
Ionaitis, R. R. - 229, 320
Isaev, P. S. - 852
Isaev, N. V. - 1042
Isaev, V. I. - 725
Ivanenko, V. V. - 808
Ivanov, A. G. - 944
Ivanov, A. P. - 1042
Ivanov, G. F. - 1024
Ivanov, G. P. - 477
Ivanov, N. S. - 998
Ivanov, N. V. - 281, 282
Ivanov, R. N. - 368, 373
Ivanov, V. B. - 1095
Ivanov, V. I. - 928
Ivanov, V. N. - 742, 930
Ivanov, V. P. - 529
Iz'yurov, A. S. - 1046
Kabachenko, A. P. - 998, 999
Kaikkonen, H. - 349
Kakurin, V. N. - 37
Kalashnik, G. V. - 14
KaPchenko, A. I. - 94
Kalebin, S. M. - 368, 373, 438
Kann, B. A. - 299, 301
Kalinin, B. N. - 818
Kalmykov, A. A. - 526
Kalyagina, I. P. - 481
Kamanin, P. M. - 1037
Kaminskii, V. A. - 563, 842
Kanderov, Yu. I. - 407
Kapitanov, V. F. - 1073
Kaptel'tsev, A. M. - 955
Karanukhov, V. A. - 1034
Karpov, V. A. - 546
Karskii, N. E. - 950
Kas'yanov, V. A. - 1066
Kas'yanov, V. F. - 570
Kaun, K. G. - 440
Kazachkov, V. I. - 638
Declassified and Approved For Release 2013/09/23: CIA-RDP10-02196R000700080005-5
Declassified and Approved For Release 2013/09/23: CIA-RDP10-02196R000700080005-5
Kazanskii, Yu. A. - 457
Kazennov, Yu. I. - 1058
Khaikovskii, A. A. - 621, 650
Khamatdinov, R. T. - 311
Kharisov, I. F. - 732
Kharitonov, I. A. - 752
Khavin, N. G. - 378
Khokhlov, V. D. - 55
Khrennikov, N. N. - 465
Khromchenko, V. B. - 727, 737
Kirienko, V. P. - 462
Kirilin, N. M. - 299, 391
Kirillov, P. L. - 353
Kirillovich, A. P. - 511
Kirilyuk, A. L. - 94
Kirsanov, G. A. - 826
Kiselr, I. M. - 1051
Kiselev, G. V. - 685
Kiselev, L. G. - 774
Kisilr, I. M. - 509
Kist, A. A. - 905
Klestova, L. M. - 1058
Klimanov, V. A. - 844
Klimenko, A. V. - 914
Klimov, Yu. I. - 118
Klinov, A. V. - 715
Klyushin, V. V. - 1078
Koblov, V. I. - 558
Kochenev, I. S. - 537
Korchuzhkin, A. M. - 1069
Kolesov, A. G. - 368, 373
Kolesov, V. F. - 194
Kolosov, K. A. - 826
Kolotyi, V. V. - 94
Kolrtsov, V. M. - 185
Komarov, N. A. - 1012
Komochkov, M. M. - 570
Kondratrev, I. A. - 996
Kondratrko, M. Ya. - 83
Kondrat'ev, V. I. - 256
Kon'kov, V. F. - 621
Konobeev, Yu. V. - 410, 796
Kononov, B. A. - 261, 924,
1014
Kononov, V. K. - 104
Konoplev, K. A. - 826
Konorova, E. A. - 574
Konovalova, N. A. - 740
Korabellnikov, B. M. - 256
Korinets, V. N. - 83
Kormushkin, Yu. P. - 715
Kornev, G. N. - 185-
Korotenko, M. N. - 840
Korotkov, S. I. - 744
Koryagin, E. V. - 1001
Koryakin, Yu. I. - 98, 154, 602,
1108
Kosenko, V. M. - 513
Koshkin, V. N. - 116
Kostritsa, A. A. - 286
Kostromin, L. G. - 360
Kotelinikov, G. N. - 643
Koternikov, Yu. A. - 1076
Kovalenko, G. D. - 421
Kovalev, V. P. - 697, 725
Koval'skii, N. G. - 110
Kovan, I. A. - 281, 282
Kozhevnikov, D. A. - 412
Kozhin, A. F. - 1037
Kozlov, S. F. - 574
Kozlov, V. F. - 867
Kozlov, V. Ya. - 687
Kozynda, Yu. D. - 206
Kozyrr, V. V. - 661
Krainov, G. S. - 256
Kraitor, S. N. - 550
Kramer-Ageev, E. A. - 837
Krapivin, M. I. - 574
Krasivina, L. E. - 997
Krasnonosen'kikh, P. P. - 818
Krasnoyarov, N. V. - 907
Kravtsev, V. V. - 943, 627
Kreindlin, I. I. - 601, 786
Kremenchugskii, L. S. - 813
Krivokhatskii, A. S. - 1072
Kruglov, A. K. - 123, 605, 963
Kruglov, S. P. - 284
Kruze, U. A. - 503
Kruzhilin, G. N. - 1
Krylov, E. A. - 1058
Krylova, N. V. - 783
Kucheryavenko, E. P. - 752
Kuchin, N. L. - 293
Kudelainen, V. I. - 50
Kuksanov, N. K. - 256
Kukushkin, A. P. - 534
Kulakov, G. A. - 247
Kulakov, G. V. - 576
Kulakov, V. M. - 987
Kuleshov, G. D. - 757
Kulibaba, V. I. - 421
Kulichenkov, A. I. - 224
Kulikov, N. Ya. - 174
Kulrkina, L. P. - 732
Kuno, I. P. - 950
Kulygin, V. M. - 882
Kurmangaliev, B. S. - 462
Kushnereva, K. K. - 550
Kustov, V. N. - 808
Kuteeva, T. M. - 752
Kutsenko, V. F. - 378
Kuzhil', A. S. - 1046
Kuzrmin, A. N. - 147
Kuzrminov, B. D. - 979
Kueminykh, V. A. - 749, 922
Kuznetsov, A. A. - 318
Kuznetsov, I. A. - 612
Kuznetsov, I. V. - 998, 999
Kuznetsov, S. A. - 256
Kuznetsov, V. M. - 818
Kuznetsov, Yu. V. - 291
Kuznetsov, Z. I. - 227
Kuznetsova, T. V. - 550
Kvochka, V. I. - 727
Labut, A. A. - 1076
Ladygin, A. Ya. -802
Laguatsov, N. I. - 834
Lantsov, M. N. - 1006
Laptsev, V. D. - 647
Lorin, E. P. - 1076
Laverov, N. P. - 178
Lavrenov, Yu. I. - 147
Lavrentovich, Ya. I. - 994
Lavrukhina, A. K. - 339
Lebedev, A. N. - 878
Lebedev, S. Ya. - 251, 1087
Lebedev, V. A. - 639
Leonov, E. S. - 550
Leontrev, G. G. - 8-74
Levin, V. N. - 204
Levinskii, Yu. V. - 805
Levishchev, A. N. - 558
Li Hen Su - 999
Likhachev, Yu. I. - 26
Linev, A. F. - 539
Lititskii, V. A. - 871
Litvin, V. F. - 1028
Logvinov, S. A. - 993
Lopatin, V. A. - 289
Lukanin, V. S. - 765
Lukryanov, A. S.- 594
Lutsenko, I. K. - 738, 744
Lytkin, V. B. - 679
Lyubchenko, V. F. - 1001, 1051
Lyudaev, R. Z. - 757
Makarchenko, V. G.- 506, 996
Maldion'kov, A. S. - 844
MaIrkov, V. V. - 570
Malykhin, A. P. - 832
MaIrtsev, I. M. - 558
Malyasova, Z. V. - 697
Malyuzhonok, D. P. - 529
Mamet, V. A. - 851
Mamontov, A. M. - 591
Mamontov, V. F. - 457
Manchuk, V. A. - 295
Manokhin, V. N. - 1100
Mardykin, I. P. - 69
Margulis, U. Ya. - 928
Markelov, I. P. - 509, 1051
1115
Declassified and Approved For Release 2013/09/23: CIA-RDP10-02196R000700080005-5
Declassified and Approved
Markina, M. A. - 637
Markov, B. N. - 429
Martinov, Yu. P. - 932
Martynov, Yu. P. - 783
Martunova, 0. I. - 933
Mashkovich, V. P. - 844
Maslov, 0. D. - 732
Matinyan, S. G. - 785
Matusevich, V. A. - 661
Matveev, V. V. - 774
Medvedev, A. V. - 14
Medvedev, Yu. A. - 55, 571, 718,
741, 906
Mel'nikov, M. V. - 462
MePnikov, V. A. - 874
Men'shikova, T. S. - 14, 37
Mesbkov, I. N. - 50
Metelkin, E. V. - 45, 718
Mikhan, V. I. - 780
Miloserdin, Yu. V. - 37
Miminov, R. A. - 423
Minashin, M. E. - 687
Mineev, V. N. - 944
Mironov, A. G. - 697
Mironov, V. N. - 1046
Mironova, E. G. - 955
MitePman, M. G. - 407, 1001
Mityaev, Yu. I. - 218
Moiseev, A. A. - 235, 600
Mokhnatkin, K. M. - 1001
Molin, G. A. - 75, 657, 1091
Morokhov, I. D. - 119
Morokhovskii, V. L. - 421
Morozov, N. N. - 55
Moshchanskaya, N. G. - 605
Moskvin, L. N. - 874
Mozhaev, V. K. - 200
Mukhachev, B. V. - 576
Mukhin, V. S. - 14
Muminov, V. A. - 917
Murtazin, 0. G. - 997
Myasnikov, K. V. - 185
Mysanikov, K. V. - 119
Nadein, V. A. - 574
Nakhutin, I. E. - 364
Nasonov, N. N. - 63
Naumov, V. I. - 465
Navalikhin, L. V. - 917
Nazaryan, V. G. - 546
Neboyan, V. T. - 693, 830
Neimotin, E. I. - 286
Nekhaev, V. E. - 342
Nekrasov, A. V. - 993
Nesterova, A. K. - 1073
Nevorotin, V. K. - 513
Nevskii, V. A. - 178
1116
For Release 2013/09/23: CIA-RDP1
Nifontov, B. I. - 185
Nikitin, V. N. - 9
Nikolaev, B. I. - 78, 563, 834
Nikolaev, V. A. - 838, 1080
Nikolaev, V. S. - 342
Nizhnik, E. I. - 994
Novgorodtsev, R. B. - 967
Novoselov, G. F. - 202, 206,
1083
Novikov, I. I.- 69
Novikov, M. Yu. - 737
Novikov, V. S. - 601
Nozhkin, A. D. - 69
Nuclei', A. M.- 558
0
Obabkov, N. V. - 572
Obaturov, G. M. - 1070
Obnoskii, V. V. - 1072
Ochkin, D. V. - 364
Odrov, Yu. L. - 185
Ogloblin, B. G. - 1071
Onufriev, V. D. - 468, 585, 955,
1055
Orlenkov, I. S. - 874
Orlov, V. V. - 1051, 1094
Pakhunkov, Yu. I. - 786
Panarin, M. V. - 75, 1091
Panasyuk, V. S. - 727
Panin, S. D. - 1087
Panin, V. I. - 202
Panov, D. A. - 113
Parkhomchuk, V. V. - 50
Parkhomov, A. G. - 837
Pavlenko, E. A. - 89
Pavlov, V. I. - 555
Pavlova, V. N. - 9
Pavlovichev, A. M. - 197, 589
Pavlovskii, A. I. - 757
Pazin, K. N. - 878
Pchelkin, V. A. - 330, 605
Pechenkin, V. A. - 796
Perekhozhev, V. I. - 1078
Pestrikov, D. V. - 50
Petrenik, 0. V. - 516
Petrov, A. I. - 9
Petrov, V. I. - 519, 687
Petrzhak, K. A. - 83, 654
Petukhov, A. A. - 14
Petushkov, A. A. - 295
Pimenov, M. K. - 677
Pinchuk, P. G. - 356
Pisarev, A. A. - 299, 301
Pitkevich, V. A. - 382, 824
Platatsis, E. Ya. - 503
Platygina, E. V. - 654
0-02196R000700080005-5
Plesch, A. G. - 220
Pleshakov, L. D. - 493
Pleve, A. A. - 528
Pliss, N. S. - 740
Plotnikov, A. L.- 261, 1014
Plyasheshnikov, A. V. - 1069
Plyutinskii, V. I. - 239
Pochivalin, G. P. - 1001
Podlazov, L. N. - 231
Polevoid, A. S. - 516
Polyachenko, A. L. - 403
Polyakov , A. A. - 920
Polyakov, V. I. - 1095
Polyukhov, V. G. - 66
Popkov, K. K. - 293
Poplavskii, V. M. - 353
Popova, G. L. - 638
Popyrin, L. S. - 166
Porollo, S. I. - 360, 802
Poruchkov, V. A. - 368
Postnikov, V. V. - 546, 939
Potapenko, P. T. - 630, 693,
830
Potekhin, N. V. - 789
Potetryunko, G. N. - 418, 746
Pozdneev, D. B. - 1089
Pozdnyakova, A. V. - 451
Pravikov, A. A. - 601
Prikot, K. N. - 1071
Privalova, P. A. - 66
Proshkin, A. A. - 1019
Prusakov, V. N. - 711
Pukolaine, G. V. - 373
Pustyl'nik, B. I. - 440
Puttlov, A. V. - 637
Pshakin, G. M. - 865
Pshenichnyi, V. A. - 89, 94
Pryankov, G. N. - 59, 60
Radyuk, R. I. - 638
Radzievskii, G. B. - 1012
Rafarskii, R. P. - 85
Rakityanskii, A. A. - 63
Rasputnis, A. M. - 174
Razinkova, T. L. - 739
Rernizoich, V. S. -72
Renard, E. V. - 521
Reviznikov, L. I. - 1058
Rimashevskii, A. V. - 37
Rivkin, E. Yu. - 40
Robakidze, N. A. - 637
Robkin, L. N. - 757
Rodionova, V. G. -251
Roginets, L. P. - 832
Romanenko, V. S.- 147
Rozanov, L. N. - 534
Declassified and Approved For Release 2013/09/23: CIA-RDP10-02196R000700080005-5
Declassified and Approved For Release 2013/09/23: CIA-RDP10-02196R000700080005-5
Rozen, A. M. - 343, 558, 703,
708, 1021
Rozenblyum, N. D. - 407, 1001
Rozenman, I. M. - 996
Rubashevskii, I. R. - 601, 786
Rudenko, A. I. - 72
Rudik, A. P. - 197, 589, 963,
1009
Rudnev, S. I. -'251
Rudoi, V. A. - 637
Rukhlo, V. P. - 920
Ruzer, L. S. - 291
Ryabov, B. M. - 1102
Ryabov, V. I. - 147
Ryabov, Yu. V. - 414, 655
Ryabukhin, V. I. - 636
Ryazanov, V. V. - 342
Rymarenko, A. I. - 1046
Rykov, V. A. - 846
Safonov, V. A. - 373
Saikov, Yu. P. - 826
Salimov, R. A. - 256, 342
Samoilov, A. G. - 451
Samsonov, B. V. - 472
Sanochkin, V. V. - 727
Sapozhnikov, A. I. - 638
Sapozhnikov, Yu. A. - 289
Sarishvili, 0. G. - 563, 842
Semenov, E. P. - 342
Semenov, Yu. P. - 506
Semenyushkin, I. N. - 318
Serebrennikov, Yu. M. - 147
Serov, A. F. - 342
Shabalin, A. N. - 306
Shabalin, E. P. - 781
Shapovalov, M. P. - 594
Sharapov, V. N. - 687, 1051
Shavarin, Yu. Ya. - 341
Shcherbak, V. I. - 360, 796,802
Shcherban', A. D. - 1067
Shchetinin, A. M. - 9
Shenderovich, A. M. - 63
Shevchenko, V. V. - 693
Shipatov, E. T. - 418
Shipilov, V. I. - 1095
Shiporskikh, Yu. M. - 407
Shirokovskii, Yu. L. - 1076
Shishkin, G. N. - 299, 301
Shishkina, Zh. A. - 826
Shitov, A. T. - 944
Shmelev, V. M. - 119
Shramenko, B. I. - 421
Shubtsov, M. I. - 837
Shukolyukov, Yu. A. - 663
Shulepin, V. S. - 1094
Shurshakova, T. N. - 481
Shvetsov, A. K. - 858
Shvetsovii, K. - 328
Shvoev, A. F. - 627
Sidorenko, V. D. - 914
Sidorov, G. I. -457
Silvenonoinen, P. - 349
Simakhin, Yu. F. - 997
Simonov, V. D. - 247, 555, 821
Sinev, A. N. - 621
Sinitsyn, A. Ya. - 206
Sinyavskii, V. V. - 462
Sirotkin, A. P. - 147
Sivintsev, Yu. V. - 790, 901
Skorov, D. M.- 297, 299, 301,
304, 306, 468, 519, 585, 909
Skovorodnikov, I. G. - 762
Skrinskii, A. N. - 50
Skulkin, N. N. - 907
Skvoev, A. F. - 243
Slesarev, I. S. - 1042
Slesarevskii, S. 0. - 840
Slezov, V. V. - 636
Slutskii, G. K. - 874
Smirnov, A. N. - 972
Smirnov, V. P. - 808
Smolin, V. N. - 535
Snitko, E. I. - 174
Sobolev, Yu. A. - 462
Sobornov, 0. P. - 115
Sokolov, P. A. - 532
Sokolovskii, L. L. - 233, 1101
Sokurskii, Yu. N. - 468, 585,
955
Soldatov, G. E. - 1001
Solodov, V. P. - 174
Solov'ev, V. A. - 356
Solov'ev, Yu. A. - 654
Sorozhuk, o. M. - 297
Spasskov, V. P. - 993
Spektor, Ya. M. - 727
Spridonov, Yu. G. - 472
Stariznyi, E. S. - 637
Stefanovskii, A. M. - 436
Stel'makh, S. S. - 840
Stepanov, B. M. - 55, 571, 727,
741, 743, 906
Storozhuk, Q M. - 468, 585
Strakovskaya, R. Ya - 59, 60,
813
Stukalov, A. I. - 820
Sukhikh, A. V. - 14
Sukhina, B. N. - 50
Sukhoruchkin, S. I. - 390
Sukhov, Yu. I. - 462
Sukhovei, V. N. - 826
Suldioverko, V. B. - 1001
Sulaberidze, G. A. - 563, 834,
842
Sulaberidze, V. Sh. - 472
Sunchagashev, M. A. - 247, 821,
Surkov, S. Ya. - 251
Suvorov, A. L. - 739
Suzdalev, I. P. - 274
Svetlov, A. V. - 304, 306, 519
Sviderskii, M. F. - 605
Sviridenko, I. P. - 1076
Svistunov, V. V. - 572
Sychev, B. S. - 765
Syltanov, A. S. - 638
Syrkus, N P. - 637
Sytov, L. I. - 14
Syuzev, V. N. - 14
Tarantin, N I. - 998, 999
Tarasko, M. Z. - 967
Tayurskii, V. A. - 80, 284
Telegin, V. I. - 882
Tenovsldi, V. G. - 299, 301
Tenishev, V. I. - 304, 306, 519
Teplov, P. V. - 995
Teplykh, V. F. - 654
Tereshkin, Yu. M. - 727, 737
Testov, I. N. - 993
Teterev, Yu. G. - 570
Teverosvskii, E. N. - 901
Tikhomirov, V: V. - 1008
Timchenko, V. L. - 14
Timofeev, G. A. - 66, 368
Timofeeva, L. F.- 594
Timoshenko, G. N. - 975
Titarenko, Yu. E. - 920
Todosiev, A. P. - 834
Tolkunov, A. E. - 178
Tomsons, E. Ya. - 503
Toporov, Yu. G. - 715
Tregubov, V. B. - 687
Tret'yak, S. A. - 364
Trofimov, I. N. - 293
Troshin, V. S. - 837
Troyan, V. I. - 78
Trushin, Yu. V. - 860, 1104
Tsarenko, A. F. - 1097
Tserevitinov, S. S. - 432
Tsypsin, S. G. - 1046
Tsykanov, V. A. - 472
Tsypkin, V. I. - 944
Tsyplenkov, V. S. - 1055
Tubin, A. A. - 563
Tuchina, A. S. - 314
Tumanov, A. A. - 1070
Tumanov, Yu. N. - 336
Ushakov, S. I. - 765
Usmanova, M. M. - 997
Usubov, Z. G. - 776
1117
Declassified and Approved For Release 2013/09/23: CIA-RDP10-02196R000700080005-5
Declassified and Approved
V
Vakhtin, A. G. - 356
Valuev, E. M.- 243, 627, 755
Vasil'ev, G. Ya. - 506
Vasil'ev, R. D. - 308
Vasil'ev, Yu. Yu. - 283
Vasin, K. D. - 185
Vasserman, S. B. - 378
Velikanov, S. P. - 727
Venikov, N. I. - 107
Verkhgradskii, 0. P. - 994
Verkhovskii, A. B. - 663
Verkhovykh, P. M. - 826
Videnskii, V. G. - 382, 824
Vikulov, V. K. - 934
Vinogradov, Yu. I. - 1083
Virgil'ev, Yu. S. - 481, 506,996
Vit'ko, V. I. - 421
Vizir', V. A. - 818
Vladimirov, V. G. - 1055
Vlasov, A. D. - 760
Vlasov, N. A. - 345, 599, 887
Vlasov, V. G. - 572
Volkov, A. P. - 867
Volkov, G. A. - 993
Volkov, V. S. - 451
1118
For Release 2013/09/23: CIA-RDP10-02196R000700080005-5
Voloozh, D. - 767
Vorob'ev, B. V. - 744
Vorob'ev, S. A. - 749, 922
Voronin, L. M. - 190, 851,
867, 1018
Vorontsov, B. A. - 147
Votinov, S. N. - 1058
Voznyuk, P. 0. - 1085
Vyropaev, V. Ya. - 732
Viyuunik, I. M. - 1085
Yagu.shkin, N. I. - 924
YakoNolev, R. M.- 819
Yakshin, V. V. - 1106
Yan'kov, G. B. - 332
Yaritsyna, I. A. - 752
Yarnya, V. P. - 308
Yaroshevich, 0. I. - 832
Yartsev, V. A. - 909
Yastreva, B. I. - 378
Yudina, V. G. - 574
Yurkin, G. B. - 939
Yuroba, L. N. - 1037
Yurova, L. N. - 465, 793, 920
Zabavin, A. K. - 1076
Zagadkin, V. A. - 1001
Zakharov, L. K. - 874
Zakutin, V. V. - 63
Zaluzhnyi, A. G. -297, 468,585
Zaraev, 0. M. - 346
Zaritskaya, T. S. - 963
Zverev, B. P. - 997
Zvezdkin, V. S. - 826
Zvontsov, A. A. - 1066
Zyabkin, V. A. - 819
Zybin, V. A. - 846
Zelenkov, A. G. - 987
Zel'venskii, M. Ya. - 703,
Zemlyanukhin, V. I. - 211
Zhamyansuren, D. - 767
Zharkovskii, E. Yu. - 190
Zhemerev, A. V. - 571, 741, 906
Zhirnov, A. D. - 147
Zhitarev, V. E. - 743
Zhuk, I. V. - 832
Zhukovskii, S. S. - 342
Zhuravleva, E. L. - 732
Zille, A. K. - 213, 849
Zubarev, V. N. - 465
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TABLES OF CONTENTS
SOVIET ATOMIC ENERGY
Volumes 40-41, 1976
(A translation of Atomnaya Energiya)
Volume 40, Number 1 January, 1976
ARTICLES
Role of Gas as a Coolant in the Development of Nuclear Power Stations
? E. P. Anan'ev and G. N. Kruzhilin
Experience in the Use of a Nuclear Reactor in the Noril'sk Mining-Metallurgical
Engl./Russ.
1 3
Complex ? V. N. Nikitin, V. N. Pavlova, A. I. Petrov, and A. M. Shchetinin. .
9
11
Testing of Experimental BN-600-Type Fuel Elements in the BOR-60 Reactor up to
Different Burnups ? M. M. Antipina, Yu. K. Bibilashvili, I. S. Golovnin,
V. M. Gryazev, E. F. Dyvydov, G. V. Kalashnik, A. V. Medvedev,
T. S. Men'shikova, V. S. Mukhin, A. A. Petukhov, A. V. Sukhikh,
V. N. Syuzev, L. I. Sytov, and V. L. Timchenko
14
16
Predicting the Efficiency (Serviceability) of Oxide Fuel Elements for Fast Sodium
Reactors ? I. S. Golovnin and Yu. I. Likhachev
26
27
In-Reactor Measurements of the Modulus of Elasticity of Uranium Dioxide
? V. M. Baranov, Yu. K. Bibilashvili, I. S. Golovnin, V. N. Kakurin,
T. S. Men'shikova, Yu. V. Miloserdin, and A. V. Rimashevskii
37
37
Hydrogen Embrittlement of Vessel Steels ? V. V. Gerasimova and E. Yu. Rivkin. . . .
40
40
Nonsteady-State Space-Energy Spectrum of Neutrons in a Heavy, Weakly Inhomogeneous
Medium, Allowing for Neutron Capture ? E. V. Metelkin
45
45
Experiments on Cooling by Electrons ? G. I. Budker,"Ya. S. Derbenev,
N. S. Dikanskii, V. I. Kudelainen, I. N. Meshkov, V. V. Parkhomchuk,
D. V. Pestrikov, A. N. Skrinskii, and B. N. Sukhina
50
49
The Use of Microwave Methods in the Dosimetry of Impulse Fluxes of Ionizing
Radiation ? Yu. A. Medvedev, N. N. Morozov, B. M. Stepanov,
and V. D. Khokhlov
55
53
DEPOSITED PAPERS
Universal Absorption Curves for a Sinusoidally Modulated Electron Beam
? R. Ya. Strakovskaya, I. R. Entinzon, and G. N. Pyankov
59
56
Dosimetry on an Object Rotating in an Electron Beam ? R. Ya. Strakovskaya,
G. N. Piyankov, and Yu. F. Golodnyi
60
57 ,
Calculations on Weakly Interacting Systems ? V. P. Ginkin
62
57
LETTERS TO THE EDITOR
Self-Acceleration Experiment of a Strong Electron Beam in a Ferrite Accelerating
Structure ? V. V. Zakutin, N. N. Nasonov, A. A. Rakityanskii,
and A. M. Shenderovich
63
59
Determination of the Half-Life of 2381311 ? V. G. Polyukhov, G. A. Timofeev,
P. A. Privalova, V. Ya. Gabeskiriya, and A. P. Chetverikov
66
61
The High-Temperature Thermal Diffusivity and Electrical Resistivity of Yttrium and
Gadolinium ? I. I. Novikov and I. P. Mardykin
69
63
Effect of Implanted Space Charge on Particle Range Distribution ? V. S. Remizovich
and A. I. Rudenko
72
64
Yields of 95mTc, 96Tc, and 971.11Tc from Irradiation of Molybdenum and Niobium
? P. P. Dmitriev, G. A. Molin, Z. P. Dmitrieva, and M. V. Panarin
75
66
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Engl./Russ.
Stimulating Isotopically Selective Heterogeneous Reactions with Laser Light
? V. D. Borman, B. I. Nikolaev, and V. I. Troyan
78
69
Efficiency for Conversion of Electrons into Positrons at 20-70 MeV
? V. A. Tayurskii
80
70
Dependence of Asymmetry in the Photofission of 233U and 239Pu on the Maximum
Bremsstrahlung ? M. Ya. Kondrat'ko, V. N. Korinets, and K. A. Petrzhak .
83
72
Synthetic Pitchblende: Composition, Structure, and Certain Properties
? V. A. Alekseev and R. P. Rafarskii
85
73
Measurement of the Energy Dependence of 77233U in the 0.02-1-eV Region
? V. A. Pshenichnyi, A. I. Blanovskii, N. L. Gnidak, and E. A. Pavlenko . . ? ?
89
76
INFORMATION
Next Problems in the Development of Oxide Fuel Elements for Fast Power Reactors
? I. S. Golovin
91
78
CONFERENCES AND SYMPOSIA
Third Conference on Neutron Physics ? A. I. KaPchenko, D. A. Bazavov,
B. I. Gorbachev, A. L. Kirilyuk, V. V. Kolotyi, V. A. Pshenichnyi,
A. F. Fedorova, and V. D. Chesnokova
94
80
Scientific Seminar on the Complex Optimization of Power Installations
? Yu. I. Koryakin
98
82
Soviet?American Seminar on Fast-Breeder Reactors ? E. F. Arifmetchikov
101
84
All-Union Conference on "Development and Application of Electron Accelerators"
? A. N. Didenko and V. K. Kononov
104
85
7th International Conference on Cyclotrons and Their Applications ? N. I. Venikov. .
107
87
Conference on Laser Engineering and Applications ? V. Yu. Baranov
and N. G. Koval'skii
110
89
Soviet?American Working Meeting on Open Traps ? D. A. Panov
113
90
International Congress on Engineering Chemistry, Chemical Engineering, and
Seventh All-Union Conference on Scintillation Technology ? 0. P. Sobornov
115
92
International Congress on Engineering Chemistry, Chemical Engineering, and
Automation ? V. N. Koshkin
116
92
REVIEWS
V. I. Sidorov, N. I. Loginov, and F. A. Kozlov ? Fundamentals of Heat Physics in
Atomic Power Installations ? Reviwed by M. Kh. Ibragimov
117
94
L. S. Sterman, L. T. Sharkov, and S. A. Tevlin, Thermal and Nuclear Power Stations
? Reviewed by Yu. I. Klimov
118
94
Volume 40, Number 2 February, 1976
ARTICLES
Peaceful Use of Nuclear Energy and the Problem of Nonproliferation of
Nuclear Weapons ? I. D. Morokhov, K. V. Mysanikov,
and V. M. Shmelev
119
99
Atomic Science and Technology in the National Economy of the USSR
? A. K. Kruglov
123
103
Experience in the Construction of Large Power Reactors in the USSR
".?
? N. A. Dollezhal' and I. Ya. Emel'yanov
137
117
Physical Start-up of the RBMK-Reactor of the Second Unit of the V. I. Lenin
Nuclear Power Station, Leningrad ? I. Ya. Emel'yanov, M. B. Egiazarov,
V. I. Ryabov, A. D. Zhirnov, ; V. P. Borshchev, B. A. Vorontsov,
A. N. Kuz 'min, Yu. I. Lavrenov, V. S. Romanenko, Yu. M. Serebrennikov,
and A. P. Sirotkin
147
127
High-Temperature Reactors as a Factor of Scientific Progress in
Power Generation ? N. A. Dollezhal' and Yu. I. Koryakin
154
133
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Methods of Mathematical Modeling and Optimization of Nuclear Power Plants
Engl./Russ.
? L. S. Popyrin
166
145
Operative Monitoring System for the Energy-Liberation Fields of the Reactors
in the Beloyarsk Nuclear-Power Station ? N. Ya. Kulikov, 1. I. Snitko,
A. M. Rasputnis, and V. P. Solodov
174
152
Structural-Geological Features of Uranium Deposits in Collapse Calderas
? V. A. Nevskii, N. P. Laverov, and A. E. Tolkunov
178
155
Continuous Underground Ore-Mining Operations with the Aid of Nuclear
Explosives ? V. V. Gushchin, K. D. Vasin, B. I. Nifontov,
Yu. L. Odrov, K. V. Myasnikov, V. M. Kol'tsov, G. N. Kornev,
and V. A. Degtyarev
185
162
INFORMATION
Atomic Energy in the USSR in the Ninth Five-Year Plan? L. M. Voronin
and E. Yu. Zharkovskii
190
167
LETTERS
Effect of Neutrons Reflected from the Walls of a Room on Pulse Parameters
In Fast Reactors ? V. F. Kolesov
194
171
Slipping Conditions in the Problem of the Minimum Critical Mass
? A. M. Pavlovichev and A. P. Rudik
197
173
Effective Half-Life of 252Cf ? V. K. Mozhaev
200
174
Measurement of the Effective Cross Section for the Fission of 252Cf by Fast
Reactor Neutrons ? E. F. Fomushkin, E. K. Gutnikova, G. F. Novoselov,
and V. I. Panin
202
176
Unusual Mineral Associations in the Oxidation Zone of Sulfide-Free Uranium
Deposits ? V. N. Levin and L. N. Belova
204
177
Effective Gamma-Ray Attenuation Coefficients for Radioactive Ores
? G. F. Novikov, A. Ya. Sinitsyn, and Yu. D. Kozynda
206
178
BOOK REVIEWS
Yu. A. Gulin. The Gamma?Gamma Method of Investigating Oil Wells? Reviewed
by E. M. Filippov
208
180
CMEA CHRONICLE
19th Conference of the CMEA Permanent Committee on Atomic Energy Use
? Yu. I. Chikul
210
181
Work of the Coordinating Scientific?Technical Council on Reprocessing
Irradiated Fuel of AES ? V. I. Zemlyanukhin
211
181
Results of the Work of the Coordinated Scientific?Technical Council on Radiation
Techniques and Technology (KNTS-RT) ? A. K. Zille
213
182
Journal of Collaboration
216
184
CONFERENCES AND MEETINGS
A Conference on the Problems of the Design, Assembly, Starting, and Operation of
Atomic Electric Power Plants ? Yu. I. Mityaev
218
185
Conference on the Technical Applications of Superconductivity ? A. G. Plesch
220
186
4th International Conference on Thermal Emission Energy Conversion
? A. I. Kulichenkov
224
188
7th European Conference on Controlled Thermonuclear Fusion and Plasma Physics
? Z. I. Kuznetsov
227
190
Soviet?West German Symposium "Armatures and Pumps for Power Stations"
? R. R. Ionaitis. .
229
192
Technical Conference Nuclex-75 ? L. N. Podlazov
231
193
Conference of Specialists on Data Processing for Reactions with Charged Particles
? L. L. Sokolovskii
233
194
24th Session of the Scientific Committee of the United Nations ? R. M. Aleksakhin
and A. A. Moiseev
235
194
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Engl./Russ.
EXHIBITIONS
Soviet Exhibitions at the 4th International Exhibition of the Nuclear Industry
Nuclex-75 ? V. A. Dolinin
237
195
BIBLIOGRAPHY
1, Ya. Emel'yanov, P. A. Gavrikov, and B. N. Seliverstov. Control and Safety
of Nuclear Power Reactors ? Reviewed by V. I. Plyutinskii
239
197
Yu. V. Seredin and V. V. Nikol'skii. Principles of Radiation Safety in Prospecting
and Exploration for Minerals ? Reviewed by E. D. Chistov
241
198
Volume 40, Number 3 March, 1976
ARTICLES
Gas-Phase Composition in the Fuel Rods at Novyi Voronezh Nuclear Power Station
? A. T. Ageenkov, A. A. Buravtsov, E. M. Valuev, L. I. Golubev, Z. V. Ershova,
V. V. Kravtsev, and A. F. Skvoev
243
203
Spatial Nonuniformity of Fuel Burnup in VVER Reactors ? L. I. Golubev,
L. I. Gorobtsov, G. A. Kulakov, V. D. Simonov, and M. A. Sunchagashev
247
207
Observation of Vacant Porosity in Metals upon Their Irradiation by Accelerated Iron
Ions ? G. N. Flerov, V. S. Barashenkov, S. Ya. Lebedev, G. N. Akap'ev,
V. E. Dubinskii, V. G. Rodionova, S. I. Rudnev, and S. Ya. Surkov
251
211
LV-1 Electron Accelerator for Industrial Use ? G. I. Budker, V. A. Gaponov,
B. M. KorabePnikov, G. S. Krainov, S. A. Kuznetsov, N. K. Kuksanov,
V. I. Kondrat'ev, and R. A. Salimov
256
216
Grazing Scattering of Fast Electrons by the Surface of a Solid? V. I. Boiko,
V. V. Evstigneev, B. A. Kononov, A. L. Plotnikov, and E. A. Gorbachev
261
221
Microdosimetric Determination of Radiation Quality Factors ? I. V. Filyushkin
267
227
The Development of Gamma-Resonance (Mossbauer) Spectroscopy in the Soviet Union
? I. P. Suzdalev
274
234
New Books from Atomizdat
280
239
DEPOSITED ARTICLES
Dynamics of Transmission of High-Frequency Power during Magnetosonic Heating
of a Plasma in a Tokamak
281
240
Applicability of the Method of Magnetosonic Heating for Thermonuclear Parameters
of a Plasma in a Tokamak
282
241
Method of Correction of Macroscopic Constants of Fast Systems Based on Results
of Individual Experiments ? Yu. Yu. Vasil'ev, V. N. Gurin, and B. G. Dubovskii .
283
242
Optimal Electron-Positron Conversion at High Energies ? V. A. Tayurskii
284
242
Calculation of Released Energy and Total Track Lengths of Charged Particles
in Showers in Xenon? M. Ya. Borkovskii and S. P. Kruglov
284
243
LETTERS
Moments of Neutron Density Distribution Functions ? A. A. Kostritsa and E. I. Neimotin
286
244
Efficiency of a Scintillation Gamma Detector in an Isotropic Radiating Medium
? Yu. A. Sapozhnikov, V. A. Lopatin, and V. P. Ovcharenko
289
246
Single-Channel Alpha Spectrometer for Measurement of Radon Daughter Product
Concentrations ? N. I. Antipin, Yu. V. Kuznetsov, and L. S. Ruzer
291
247
Algorithm for Monte Carlo Simulation of Compton Scattering Including Gamma-Ray
Polarization ? N. L. Kuchin, K. K. Popkov, and I. N. Trofimov
293
249
Semiconductor Radiometer-Spectrometer for Measurement of Surface Contamination
by Alpha-Radioactive Materials ? V. A. Manchuk and A. A. Petushkov
295
250
An Apparatus for Assaying Helium in Constructional Materials ? A. I. Dashkovskii,
A. G. Zaluzhnyi, D. M. Skorov, 0. M. Sorozhuk, and M. V. Cherednichenko-
Alchevskii
297
251
1122
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Surface Blister Bursting B. A. Kahn, N. M. Kirilin, A. A. Pisarev, D. M. Skorov,
Engl./Russ.
V. G. Tel'kovskii, S. K. Fedyaev, and G. N. Shishkin
299
252
Temperature Dependence of Erosion of Stainless Steels under Ionic Bombardment
? A. D. Gurov, B. A. Kahn, N. M. Kirilin, A. A. Pisarev, D. M. Skorov,
V. G. TePkovskii, S. K. Fedyaev, and G. N. Shishkin
301
254
Diffusion Coefficients and Solubility of Vanadium, Niobium, and Cerium in Beryllium
? V. M. Anantin, V. P. Gladkov, A. V. Svetlov, D. M. Skorov, and V. I. Tenishev ? ?
304
256
Diffusion and Solubility of Aluminum in Beryllium ? V. P. Gladkov, A. V. Svetlov,
D. M. Skorov, V. I. Tenishev, and A. N. Shabalin
306
257
Relative Measurements of the Spectral Characteristics of Neutron Distributions
by the Activation Ratios Method? R. D. Vasil'ev, E. I. Grigor'ev, and V. P. Yarnya
308
259'
Monte Carlo Solution of Gamma?Gamma Logging Problems for Large Distances
from the Source ? R. T. Khamatdinov
311
260
COMECON CHRONICLES
Symposium on "The Drawing-Up of Apparatus Systems of Nuclear Instrument Making
for Laboratory and Industrial Applications ? A. S. Tuchina
314
263
Comecon Collaboration Notes
316
264
INFORMATION
50 Years of Corresponding Member of the Academy of Sciences of the SSSR,A.M.Baldin
? N. N. Bogolyubov, A. A. Kuznetsov, and I. N. Semenyushkin
318
265
CONFERENCES AND MEETINGS
Seminar onthe Operating Cycles of Nuclear Power Stations ? B. B. Baturov,
0. M. Glazkov, and R. R. Ionaitis
320
266
International Symposium on Gas-Cooled Reactors ? I. Kh. Ganev
323
267
The Soviet? French Seminar on Water-Cooled/Water-Moderated Power Reactors
? V. P. Denisov
326
269
Symposium on the Transplutonium Elements ? K. Shvetsovii
328
270
IAEA Symposium on the Natural Nuclear Reactor at Oklo ? V. A. Pchelkin
330
271
Conference of the International Committee on Nuclear Data ? G. B. Yan'kov
332
272
All-Union Conference on the Application of Charged-Particle Accelerators
in the National Economy ? 0. A. Gusev
334
273
2nd International Symposium on Plasma Chemistry ? Yu. N. Tumanov
336
274
3rd International Conference on the Measurement of Low Levels of Radioactivity
and Their Application ? A. K. Lavrukhina
339
275
All-Union Seminar on the Radiation Stability of Organic Materials ? Yu. Ya. Shavarin .
341
277
NEW FACILITIES
A Facility for Producing a Beam of Electrons with Energies of up to 250 KeV
and with a Power of Up to 1000 kW? M. M. Brovin, A. A. Bushuev, V. A. Gapanov,
A. I. Grishehenko, S. S. Zhukovskii, V. E. Nekhaev, V. S. Nikolaev,V.V.Ryazanov,
R. A. Salimov, E. P. Semenov, and A. F. Serov
342
277
BIBLIOGRAPHY
A. I. Moskvin. Coordination Chemistry of the Actinides ? Reviewed by A. M. Rozen ? ? ?
343
278
V. M. Gorbachev, Yu. S. Zamyatnin, and A. A. Lbov. The Principal Characteristics
of Isotopes of the Heavy Elements ? Reviewed by N. A. Vlasov
345
278
A. P. Zimon. Decontamination? Reviewed by 0. M. Zaraev
346
279
Volume 40, Number 4 April, 1976
ARTICLES
Plutonium Charging of the VVER-440 Water-Cooled Water-Moderated Reactor
? H. Kaikkonen and P. Silvennoinen
349
283
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Engl./Russ.
Design of Sodium?Water Steam Generators ? P. L. Kirillov and V. M. Poplavskii ? ?
Nature and Thermal Stability of Radiation-Induced Defects in Zirconium Hydride
? P. G. Pinchuk, V. N. Bykov, G. A. Birzhevoi, Yu. V. Alekseev,
A. G. Vakhtin, and V. A. Solov'ev
Empirical Relationship between the Swelling of OKh16N15M3B Steel and Irradiation
Dose and Temperature ? V. N. Bykov, V. D. Dmitriev, L. G. Kostromin,
S. I. Porollo, and V. I. Shcherbak
The Adsorption of Krypton and Xenon at Low Partial Pressures on Industrial Samples
of Activated Carbon ? I. E. Nakhutin, D. V. Ochkin, S. A. Tret'yak,
and A. N. Dekalova
Total Neutron Cross Section and Neutron Resonance Parameters of 243Am in the Energy
Range 0.4-35 eV ? T. S. Belanova, A. G. Kolesov, V. A. Poruchikov,
G. A. Timofeev, S. M. Kalebin, V. S. Artamonov, and R. N. Ivanov
Total Neutron Cross Section and Neutron Resonance Parameters of 24IAm in the Energy
Range 0.004-30 eV ? S. M. Kalebin, V. S. Artamonov, R. N. Ivanov,
G. V. Pukolaine, T. S. Belanova, A. G. Kolesov, and V. A. Safonov
The Pulsed ELIT-1BElectronAccelerator ? Yu. G. Bamburov, S. B. Vasserman,
V. M. Dolgushin, V. F. Kutsenko, N. G. Khavin, and B. I. Yastreva
Cross Sections of the Interaction of Protons and Electrons with Atoms of Hydrogen,
Carbon, Nitrogen, and Oxygen ? V. A. Pitkevich and V. G. Videnskii
Pulsed Neutron Sources for Measurement of Nuclear Constants ? S. I. Sukhoruchkin.
DEPOSITED PAPERS
Asymptotic Neutron Distribution in a Nonmultiplying Two-Zone Cylindrical Medium
? A. L. Polyachenko
Neutron Importance Function in Heterogeneous Reactors ? V. A. Dulin
LETTERS
In-Core System for Automatic Power Control of IRT-M Reactor ? L. G. Andreev,
Yu. I. Kanderov, M. G. Mitel'man, N. D. Rozenblyum, V. P. Chernyshevich,
and Yu. M. Shiporskikh
Determination of Irradiation Temperature from Measurement of Lattice Constant of
Radiation Voids ? Y. V. Konobeev
Slowing Down of Resonance Neutrons in Matter ? D. A. Kozhevnikov
Measurement of a in the Resonance Region ? Yu. V. Ryabov
Ionization Energy Losses and Ranges of Alpha Particles in Ionic Crystals
? G. N. Potetyunko and E. T. Shipatov
A Monochromatic Annihilation Gamma-Ray Beam from a 2-GeV Linear Electron
Accelerator ? B. I. Shramenko, G. L. Bochek, V. I. Vit'ko, I. A. Grishaev,
V. I. Kulibaba, G. D. Kovalenko, and V. L. Morokhovskii
Parameters of Semi-Insulating GaAs Nuclear-Radiation Detectors ? S. A. Azimov,
S. M. Bukki, R. A. Miminov, and U. V. Shchebiot
COMECON DIARY
Sixth International Conference on Messbauer Spectroscopy ? A. G. Beda
BIB LI OGRA PHY
A. A. Moiseev and P. G. Ramzaev ? Cesium-137 in the Biosphere ? Reviewed by
R. M. Aleksakhin
INFORMATION: CONFERENCES AND MEETINGS
The Second International Conference on Sources of Highly Charged Ions ? B. N. Markov.
The Third International Conference on Impulse Plasma with High I ? S. S. Tserevitinov.
A Soviet ?American Project for a Diverter for a Tokamak Reactor ? A.M. Stefanovskii.
A Conference on Nuclear Data for Transactinoidal Elements ? S. M. Kalebin
An International School-Seminar on the Interactions of Heavy Ions with Nuclei and the
Synthesis of New Elements ? K. G. Kaun and B. I. Pustyl'nik
1124
353
286
356
289
360
293
364
295
368
298
373
303
378
308
382
311
390
318
403
332
405
333
407
335
410
337
412
338
414
339
418
343
421
345
423
346
425
349
428
351
429
352
432
353
436
356
438
357
440
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Volume 40, Number 5 May, 1976
From the Proceedings of the 25th Congress of the Communist Party of the Soviet
Engl./Russ.
Union
445
363
20 Years of the Journal ''Atomnaya Energiyall
448
367
ARTICLES
Steam-Superheating Fuel Elements of the Reactors in the I. V. Kurchatov
Beloyarsk Nuclear Power Station ?A. G. Samoilov, A. V. Pozdnyakova,
and V. S. Volkov
451
371
Some Physical Investigations in BFS-1 Fast Critical Assemblies
?V. A. Dulin, Yu. A. Kazanskii, V. F. Mamontov, and G. I. Sidorov
457
377
Some Results of Postreactor Testing of Six-Element Thermionic Units Operating
for 2670 h ? G. A. Batyrbekov, E. S. Bekmukhambetov, V. I. Berzhatyi,
S. E. Ermatov, Sh. Sh. Ibragimov, V. P. Kirienko, B. S. Kurmangaliev,
M. V. Mel'nikov, V. V. Sinyavskii, Yu, A. Sobolev, and Yu. I. Sukhov
462
382
Effect of Heterogeneity on the Measurement of Integral Parameters
in Subcritical Systems ? L. N. Yurova, A. V. Bushuev, V. I. Naumov,
V. M. Duvanov, N. N. Khrennikov, and V. N. Zubarev
465
384
Investigation of the Liberation of Helium from Construction Materials
during Their Heating ?D. M. Skorov, N. P. Agapovap A. I. Dashkovskii,
Yu. N. Sokurskii, A. G. Zaluzhnyi, 0. M. Storozhuk, V. D. Onufriev,
and I. N. Afrikanov
468
387
The Evolution of Gas from Uranium Dioxide ? B. V. Samsonov, Yu. G. Spridonov,
V. Sh. Sulaberidze, and V. A. Tsykanov
472
390
Sputtering of Thin Films of Uranous?Uranic Oxide under the Influence of Fission
Fragments at Low Irradiation Doses ? V. A. Bessonov, G. P. Ivanov,
N. A. Grinevich, and E. A. Borisov
477
395
REVIEWS
Radiation Defects in Graphite ? T. N. Shurshakova, Yu. S. Virgil'ev,
and I. P. Kalyagina
481
399
DEPOSITED PAPERS
Asymptotic Solution of a y-Ray Transport Equation ? L. D. Pleshakov
493
411
LETTERS TO THE EDITOR
Correction for Time of Fall in Negative-Reactivity Determination by Rod-Drop
?O. A. Elovskii
500
418
An Investigation of the Parameters of a Critical Assembly ? E. Ya. Tomsons,
V. V. Bute, V. V. Gavar, A. S. Dindun, U. A. Kruze, and E. Ya. Platatsis
503
420
Ampule Devices in the VVR-M Reactor for Irradiating Carbon-Based
Materials ? G. Ya. Vasil'ev, Yu, S. Virgil'ev, V. G. Makarchenko,
and Yu. P. Semenov
506
423
Neutron-Spectrum Structure near a Resonant Absorption Line ? A. I. Dodt,
I. M. KisiP, and I. P. Markelov
509
425
Calorimeter Measurement of the Heat Released by Irradiated Nuclear Fuel
?A. P. Kirillovich, P. S. Gordienko, and V. P. Buntushkin
511
427
Structural Changes in Irradiated Dysprosium Titanate ? V. M. Kosenkov,
T. M. Guseva, S. A. Alekseeva, and V. K. Nevorotin
513
428
Separation of Isotopic Mixtures of Hydrogen in the Hydrogen?Palladium System
? B. M. Andreev, A. S. Polevoi, and 0. V. Petrenik
516
431
Magnetic Susceptibilities of Beryllides ? V. P. Gladkov, V. I. Petrov, A. V. Svetlov,
D. M. Skorov, and V. L Tenishev
519
433
CONFERENCES AND MEETINGS
Radiochemistry and Nuclear Technology on the 11th Mendeleev Congress
of General and Applied Chemistry ?E. V. Renard
521
435
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Engl./Russ.
Use of Radioisotope Techniques and Instruments in Machine Construction
-M. L. Golldin
525
438
The Annual Conference of the Plasma Physics Division of the American Physical
Society -A. A. Kalmykov
526
439
IN INSTITUTES AND DESIGN OFFICES
Acceleration of "Ca Ions and New Possibilities of Synthetizing Superheavy Elements
-A. A. Pleve
528
440
The Operator-Stereotelevision-Manipulator System in Nuclear Power Generation
- Yu. A. Gerasimov, V. P. Ivanov, and D. P. Malyuzhonok
529
441
EXHIBITIONS
New Exhibits in the Hall "Atomic Energy" the Exhibition of Achievements
of the National Economy of the USSR - P. A. Sokolov
532
443
BOOK REVIEWS
A. A. Glazkov, I. F. Malyshev, and G. L. Saksaganskii. Vacuum Systems
for Electrophysical Apparatus - Reviewed by A. P. Kulcushkin and L.N.Rozanov .
534
445
V. I. Subbotin, M. Kh. Ibragimov, P. A. Ushakov, V. P. Bobkov, A. V. Zhukov,
and Yu. S. Yur'ev. Hydrodynamics and Heat Exchange in Atomic-Power
Installations - Reviewed by V. N. Smolin
535
445
B. V. Lysikov, V. K. Prozorov, V. V. Vasil'ev, D. N. Popov, L. F. Gromov,
and Yu. V. Rybakov. Temperature Measurements in Nuclear Reactors
- Reviewed by I. S. Kochenev
537
446
Volume 40, Number 6 June, 1976
The Kiev 240-cm Isochronous Cyclotron - A. F. Linev
539
451
Investigation of the Random Component of the Heat-Release Distribution in a Nuclear
Reactor - V. A. Karpov, V. G. Nazaryan, and V. V. Postnikov
546
456
Spectra of Fast Neutrons from a Pulsed Reactor - G. G. Doroshenko, S. N. Kraitor,
T. V. Kuznetsova, K. K. Kushnereva, E. S. Leonov, and G. A. Frolova
550
460
Numerical Investigation of the Optimum Conditions for the Power Reduction of a
Reactor - V. M. Desyatov, V. I. Pavlov, and V. D. Simonov
555
464
Development of an Apparatus for Clarifying Solutions Prior to the Extraction
Reprocessing of VVER Fuel Elements - A. M. Rozen, K. A. Dolgova,
A. M. Nudel', I. M. Balakin, I. M. Mal'tsev, V. I. Koblov, A. N. Levishchev,
and B. R. Borisov
558
467
Theory of a Mass-Diffusion Separative Unit - V. A. Chuzhinov, V. A. Kaminskii,
B. I. Nikolaev, 0. G. Sarishvili, G. A. Sulaberidze, and A. A. Tubin
563
471
DEPOSITED ARTICLES
Induced Activity of Building and Structural Materials in the 680-MeV Synchrocyclotron
Hall - V. F. Kas'yanov, M. M. Komochkov, Yu. G. Teterev, and V. V. Mal'kov . . .
570
478
Calculations of Some Characteristics of the y -Radiation Field Induced in Air by Fast
Neutrons - A. V. Zhemerev, Yu. A. Medvedev, and B. M. Stepanov
571
479
Electrochemical Behavior of Metals in the Radiation Field of a Nuclear Reactor
- G. Z. Gochaliev and S. I. Borisova
571
479
Production and Study of Corrosion Resistance in Zirconium Diboride and its Solid
Solutions with Titanium Diboride - V. V. Svistunov, A. R. Beketov, V. G. Vlasov,
and N. V. Obabkov
572
480
Thermalization of Neutrons in Solids - V. A. Baikulov
573
480
LETTERS
Using Diamond Detectors as Immersed a Counters - S. F. Kozlov, E. A. Konorova,
M. I. Krapivin, V. A. Nadein, and V. G. Yudina
- 574
482
Sensitivity of Emission Detectors to Rays - G. V. Kulakov and B. V. Mukhachev
576
483
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Migration of Radiogenic Lead in the Hydrothermal Metamorphism of Uranium Minerals
Engl./Russ.
? V. M. Ershov
579
485
Quantitative Analysis of Various Factors Affecting the Intensity of the X-Ray Signal
Backscattered from a Semiinfinite Reflector ? F. L. Gerchikov ? . ?
581
487
Liberation of Helium in the Uniform Heating of Neutron-Irradiated OKh16N15M3B
Steel ? N. P. Agapova, I. N. Afrikanov, A. I. Dashkovskii, A. G. Zaluzhnyi,
V. D. Onufriev, D. M. Skorov, Yu. N. Sokurskii, and 0. M. Storozhuk
585
490
Search for Fissile Isomers in the (n, 2n) Reaction ? J. S. Browne R. E. Houve
587
491
Optimal Arrangement of Effective Absorber in a Reactor ? A. M. Pavlovichev
and A. P. Rudik
589
493
Evaluation of Dose Rate from Radiation Heating of a Sample during Irradiation
? A. P. Balashov and A. M. Mamontov
591
494
The Crystal Structure of the Compounds Pu5Rh4 and Pu5Ir4 ? A. V. Beznosikova,
N. T. Chebotarev, A. S. Luk'yanov, M. P. Shapovalov, and L. F. Timofeeva
594
495
NEWS ITEMS FROM THE COUNCIL FOR MUTUAL ECONOMIC AID (CEMA)
Diary of Collaboration
597
499
INFORMATION
The I. V. Kurchatov Gold Medal Competition
598
500
Still No "Cosmion" ?N. A. Vlasov
599
500
Conference of the Fourth Committee of the International Commission on Radiological
Protection (ICRP) ? A. A. Moiseev
600
501
The Beta-Mikrometr-3 Double-Layer Coating Radioisotope Thickness Gauge
? I. I. Kreindlin, V. S. Novikov, A. A. Pravikov, and I. R. Rubashevskii .
?
601
501
BOOK REVIEWS
A. M. Petrostyants. Nuclear Power Generation ? Reviewed by Yu. I. Koryakin
602
503
Volume 41, Number 1 July, 1976
ARTICLES
Natural Nuclear Reactor in Oklo (Gabon) ? A. K. Kruglov, V. A. Pchelkin,
M. F. Sviderskii, N. G. Moshchanskaya, 0. K. Chernetsov, and
Yu. M. Dymkov
605
Studying the Interaction of Molten Fuel with Sodium in the Active Zone of a Fast
Reactor ? Yu. K. Buksha, Yu. E. Bagdasarov, and I. A. Kuznetsov
612
9
Estimate of the Corrosion of Zirconium Alloys under Operating Conditions
? V. V. Gerasimov, A. I. Gromova, and V. G. Denisov
617
14
Effect of the Presence of Kh18N1OT Steel on the Corrosion Stability of Zirconium
Alloys ? V. F. Kon'kov, A. N. Sinev, and A. A. Khaikovskii
621
17
Determination of the Content of Tritium and Krypton in VVER Fuel Elements and a Study
of Their Distribution in the Preparatory Operations Fuel Elements for
,of
Reprocessing? A. T. Ageenkov, A. A. Buravtsov, E. M. Valuev, L. I. Golubev,
Z. V. Ershova, V. V. Kravtsev and A. F. Shvoev
627
23
Mathematical Models of the Neutron Distribution in a Reactor
? P. T. Potapenko
630
25
DEPOSITED ARTICLES
The Distribution of Moving Holes in a Material with Sources of Gas Atoms
? V. V. Slezov and V. I. Ryabukhin
636
31
Effect of the Distribution of Neutron Flux in the Active Zone on Irradiation
Intensity of Uranium Radiation Contour ? A. V. Putilov, M. A. Markina,
N. A. Robakidze, V. A. Rudoi, E. S. Stariznyi, and N. P. Syrkus
637
31
Deactivation of Weakly Active Discharge Waters by Fibrous Ionites
? G. L. Popova, R. I. Radyuk, A. S. Syltanov, and B. E. Geller
638
32
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Engl./Russ.
Errors of a Fluctuation-Type Reactor Power and Period Meter ? A. I. Sapozhnikov
and V. I. Kazachkov
638
33
Thermodynamic Properties of Liquid Alloys of Actinides and Lanthanides
? V. A. Lebedev
639
33
LETTERS
Numerical Buildup Factors and Average y-Spectrum Energy behind Scattering
Media ? A. A. Gusev
641
35
Quantitative Relationships of Tantalum, Radioactive Elements, and Zirconium
in Rare-Metal Ores ? G. N. Koteltnikov
643
36
Analysis the Spectral
645
38
of Composition of X-Ray-Signals Backscattered
from Various Surfaces ? F. L. Gerchikov. 0. . .
Estimating the Nuclear Safety of Systems of Subcritical Assemblies by the
Interaction-Parameter Method? V. D. Laptsev and Yu. I. Chernukhin .
647
39
Texture in Oxide Films on Zirconium and Binary Zirconium?Tin and
Zirconium?Titanium Alloy Single Crystals ? F. P. Butra and
A. A. Khaikovskii
650
42
Relative Yields of Xenon Isotopes in the Photofission of 227Np and 235U
? K. A. Petrzhak, E. V. Platygina, Yu. A. Solov'ev, and
V. F. Teplykh
654
44
Measurement of a (E) = c(E)/af(E) of 239Pu for 0.007-eV-12-keV Neutrons
? Yu. V. Ryabov
655
45
Yields of 73As and 74As in Nuclear Reactions with Protons, Deuterons, and a Particles
? P. P. Dmitriev and G. A. Molin
657
48
Nondestructive Analysis of Thin Surface Layers of Materials for Hydrogen Content
? I. P. Chernov, V. V. Kozyr', and V. A. Matusevich..
661
51
Anomalous Isotope Composition of Xenon and Krypton in Minerals of the Natural
Nuclear Reactor ? Yu. A. Shukolyukov, G. Sh. Ashkinadze, and
A. B. Verkhovskii
663
53
COME CON DIARY
Cooperation Notes
667
56
CONFERENCES AND SEMINARS
39th Session of the Scientific Council of the All-Union Institute of Nuclear Research
?V. A. Biryukov
671
59
Seminar on the Prospects for Development of Secondary Power Sources
in Nuclear Instrument Construction ? A. F. Belov .
675
61
Conference of Experts of the International Atomic Energy Agency (IAEA) on
the Treatment of Radioactive Wastes ? M. K. Pimenov
677
64
The Second Session of the Soviet?American Coordination Commission on Fast
Reactors ? V. B. Ly-tkin and E. F. Arifmetchikov
679
65
Soviet?American Seminar on the Safety of Fast Reactors ? Yu. E. Bagdasarov. .
682
67
Seminar on General Purpose and Special Accessories for Nuclear Power Stations
? G. V. Kiselev
685
69
Volume 41, Number 2 August, 1976
ARTICLES
Experience in the Operation of Channels with Single-Pass Steam Generation in the Reactor
at the First Nuclear Power Station ? V. V. Dolgov, V. Ya. Kozlov,
M. E. Minashin, V. D. Petrov, V. B. Tregubov, and V. N. Sharapov
687
75
Zone Regulation of the Power of a Power Reactor ? I. Ya. Emel'yanov, E. V. Eilipchuk,
A. G. Filippov, V. V. Shevchenko, P. T. Potapenko, and V. T. Neboyan
693
81
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Engl./Russ.
Redistribution and Mobility of Uranium during the Metamorphism of Volcanogenic
Formations ? V. P. Kovalev, A. D. Nozhkin, A. G. Mironov, and Z. V. Malyasova
697
85
Mathematical Simulation of Processes in the Extractive Reprocessing of Nuclear Fuel.
4. Separation of Uranium and Plutonium by the Method of Displacement
Re-Extraction ? A. M. Rozen and M. Ya. Zel'venskii
703
91
Mathematical Simulation of Processes in the Extractive Reprocessing of Nuclear Fuel.
5. Separation of Uranium and Plutonium by the Method of Re-Extraction with a Weak
Acid ? A. M. Rozen and M. Ya. Zel'venskii
708
95
Liquid ?Vapor Equilibrium in Systems with Dilute Solutions of Metal Fluorides in
Uranium Hexafluoride ? V. N. Prusakov, V. K. Ezhov, and E. A. Efremov
711
98
Distribution of the Losses during the Accumulation of Isotopes of the Transuranium
Elements ? Yu. P. Kormushkin, A. V. Klinov, and Yu. G. Toporov
715
102
Slowing Down of Particles in Highly Anisotropic Scattering. Statistical Fluctuations of
Energy Losses in Collisions ? Yu. A. Medvedev and E. V. Metelkin
718
105
Total Backscattering Coefficients for Obliquely Incident 15-25-MeV Electrons
? V. V. Gordeev, V. P. Kovalev, and V. I. Isaev
725
110
50-MeV Electron Synchrotron with Cyclotron Preacceleration ? S. P. Velikanov,
V. I. Kvochka, V. S. Panasyuk, V. V. Sanochkin, Ya. M. Spektor, B. M. Stepanov,
Yu. M. Tereshkin, and V. B. Khromchenko
727
113
Prospects for the Use of Nuclear-Physics Analytic Methods in Biology as Illustrated by
the Wilt Problem ? V. Ya. Vyropaev, I. F. Kharisov, 0. D. Maslov,
E. L. Zhuravleva, and L. P. Kul'kina
732
118
DEPOSITED ARTICLES
Problem of the Intensity of an Electron Synchrotron with Cyclotron Preacceleration ?
M. Yu. Novikov, Yu. M. Tereshkin, and V. B. Khromchenko
737
125
Effect of Hard Ore-Enclosing Rock on the Efficiency of Underground Leaching
?I. K. Lutsenko, A. A. Burykin, and V. K. Bubnov
738
126
Interpretation of Autoionic Images of the Dislocation Structure of Uranium by Means of a
Computer ? A. L. Suvorov and T. L. Razinkova
739
127
Determination of the Degree of Sensitivity of Mass-Spectrometers to Microimpurities
-7M. L. Aleksandrov, N. A. Konovalova and N. S. Pliss
y Field Initiated by a Monodirectional Neutron Source in Air ? A. V. Zhemerev,
Yu. A. Medvedev, and B. M. Stepanov
740
741
128
129
Basic Laws for the Formation of Tissue Doses from Collimated Beams of Monoenergetic
Neutrons ?V. N. Ivanov
742
129
Total Cross Section for the Interaction of Cold Neutrons with Water ? S. B. Stepanov
and V. E. Zhitarev
743
130
LETTERS TO THE EDITOR
Effect of the Composition of Friable Ore-Bearing Rocks on the Effectiveness of the
Process of Underground Leaching ?A. A. Burykin, I. K. Lutsenko,
B. V. Vorob'ev, and S. I. Korotkov
744
132
Determination of Specific Energy Losses by Charged Particles in Matter
? G. N. Potetyunko
746
134
Use of "Beam Unfolding" for Calculation of 0-Flux Absorption in the Segment Model
? V. A. Kuz'minykh and S. A. Vorob'ev
749
136
Measurement of Spectral Characteristics of Slow-Neutron Fields Using Cadmium Ratios
of Activation Detectors ? I. A. Yaritsyna, E. P. Kucheryavenko, I. A. Kharitonov,
and T. M. Kuteeva
752
138
Investigation of the Removal of T and 85Kr during Processing of Irradiated UO2 in an
"
Oxygen Medium ? A. T. Ageenkov and E. M. Valuev
755
140
Pulsed Air-Cored Betatron Powered from a Magnetocumulative Generator
? A. I. Pavlovskii, G. D. Kuleshov, R. Z. Lyudaev, L. N. Robkin,
and A. S. Fedotkin
757
142
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Engl./Russ.
Increase in Beam Radius and Size of Image Ellipsoid because of Errors in a Linear
Proton Accelerator ? A. D. Vlasov
760
144
Flowmeter with Radiation Detector for Wells ? I. G. Skovorodnikov
762
146
Radioactivity of the Water in the Ground Shield of Accelerators ? V. D. Balukova,
V. S. Lukanin, B. S. Sychev, and S. I. Ushakov
765
148
Effect of y Radiation of Presown Seeds on the Crop Yield and Productivity of Open-Ground
Tomatoes under the Conditions of the Mongolian Peoples Republic ? D. Voloozh
and D. Zhamyansuren
767
149
INFORMATION
Jubilee Celebrations at Dubna ?A. I. Artemov
770
153
Standards of the International Electrotechnical Commission in Nuclear Instrument
Manufacture ? V. V. Matveev and L. G. Kiselev
774
156
CONFERENCES AND MEETINGS
New Materials and Progressive Technology in the Production of Plants for Nuclear
Power Stations ? Z. G. Usubov
776
157
Seminar on Water-Cooled/Water-Moderated Reactors in France ? A. D. Amaev
and V. N. Filippov
778
158
International Congress on Reactors ? V. I. Mikhan
780
160
American ?Japanese Seminar on the Planning, Operation, and Use of Pulsed Fast
Reactors ? E . P. Shabalin
781
161
Symposium on the Treatment of Radioactive Waste from the Nuclear Fuel Cycle
? N. V. Krylova and Yu. P. Martynov
783
161
The Seventh Spring Seminar on High-Energy Physics ? S. G. Matinyan
785
163
INS TRU1V1E NTS
The GUPS-1 Immersion Follower y-Level Gauge ? I. I. Kreindlin, Yu. I. Pakhunkov,
and I. B. Rubashevskii
786
163
REVIEWS
S. V. Mamikonyan. Equipment and Methods of Fluorescent X-Ray Radiometric Analysis
?Reviewed by E . M. Filippov
788
165
I. K. Morozova, A. I. Gromova, V. V. Gerasimov, V. A. Kucheryaev,
and V. V. Demidova. The Loss and Deposition of Corrosion Products of Reactor
Materials ?Reviewed by N. V. Potekhin
789
166
N. D. Tyufyakov and A. S. Shtan'. Principles of Neutron Radiography ? Reviewed by
Yu. V. Sivintsev
790
166
Volume 41, Number 3 September, 1976
ARTICLES
Measurement of Resonance Escape Probability ? L. N. Yurova, A. V. Bushuev,
and V. M. Duvanov
793
171
Kinetics of Annealing of Radiation Pores in OKh18N9T Stainless Steel, Irradiated by
Neutrons ? V. A. Pechenkin, Yu. V. Konobeev, and V. I. Shcherbak
796
174
Effect of the Interaction of OKh18N9T Steel with the Coolant on the Development of Porosity
in the Fuel Cluster Sheath of the BR-5 Reactor ? V. I. Shcherbak, V. N. Bykov,
V. D. Dmitriev, S. I. Porollo, and A. Ya. Ladygin
802
179
The p? T Diagram of the Uranium?Carbon System ? Yu. V. Levinskii
805
182
Thermal Cross Section and Resonance Integrals of Fission and Capture of 241AM, 243Am,
245cm, 24 9Bk, and 249Cf ? V. D. Gavrilov, V. A. Goncharov, V. V. Ivanenko,
V. N. Kustov, and V. P. Smirnov
808
185
Using Pyroelectric Detectors for the Dosimetry of Pulsed y Radiation
? L. S. Kremenchugskii and R. Ya. Strakovskaya
813
190
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DEPOSITED AR TIC LE S
Choice of Optimal Dimensions for a Synchrotron Bremsstrahlung Target ? V. A. Vizir',
B. N. Kalinin, V. M. Kuznetsov, and P. P. Krasnonosen'kikh
The Role of Nuclear Cascades in the Formation of Neutrons in Pb, Cd, Fe, Al and Fission
of Lead Nuclei by the Action of Cosmic Radiation at Various Depths below the Earth
? V. A. Zyabkin and R. M. Yakov'lev
Effect of Thermomechanical Processing on the Amplitude-Dependent Internal Friction of
Uranium ? A. I. Stukalov, G. S. Gaidamachenko, and A. V. Azarenko
Two Methods of Determining Fuel Burnup by y Spectrometry ? L. I. Golubev,
L. I. Gorobtsov, V. D. Simonov, and M. A. Sunchugashev
Singular Equations and Conditions of Solvability of Boundary Problems in the Theory of
Neutron Transfer ? B. D. Abramov
LETTERS TO THE EDITOR
Interpretation of Instrument Lines of an Ionization Pulse Spectrometer Suitable for
Microdosimetry ? V. A. Pitkevich and V. G. Videnskii
Planning the Reconstruction of the Active Zone of a VVR-M Reactor ? P. M. Verldiovykh,
V. S. Zvezdkin, G. A. Kirsanov, K. A. Kolosov, K. A. Konoplev, Yu. P. Saikov,
V. N. Sukhovei, T. A. Chernova, and Zh. A. Shishkina
Analysis of On ?Off Zonal Reactor Control Systems ? E. V. Filipchuk, V. T. Neboyan,
and P. T. Potapenko
Efficiency of Detection of Fission Fragments by Solid Track Detectors ? A. P. Malykhin,
I.,V. Zhuk, 0. I. Yaroshevich, and L. P. Roginets
Limits of Applicability of Weak-Enrichment Approximation for Cascade Separation of
Two-Component Mixtures ? N. I. Laguntsov, B. I. Nikolaev, G. A. Sulaberidze,
and A. P. Todosiev
Neutron Detection with Hydrogenous Detectors ? E. A. Kramer-Ageev, A. G. Parldiomov,
V. S. Troshin, and M. I. Shubtsov
Additivity Deviations in the Thermal and Radiation-Induced Embrittlement of Steel under
Neutron Irradiation ? V. I. Badanin and V. A. Nikolaev
The Transient Response in the emf of a Thermocouple under Reactor Conditions
? M. N. Korotenko, S. 0. Slesarevskii, and S. S. Stel'makh
Measurement of the Enrichment Factor in Relation to Flow Distribution in a Separation
System ? V. A. Kaminskii, 0. G. Sarishvili, G. A. Sulaberidze, V. A. Chuzhinov,
and B. Sh. Dzhandzhgaba
Characteristics of Neutron Radiation Reflected from Concrete ? V. A. Klimanov,
A. S. Makhon'kov, and V. P. Ma shkovich
Tritium Content in Liquid Media and in Air of Working Locations at Nuclear Power Stations
?Yu. P. Abolmasov
Analytic Representation of Ion Energy Loss in Stopping by Nuclei ? V. A. Zybin
and V. A. Rykov
COMECON NEWS
The Interatominstrument Exhibition ? V. A. Dolinin
International Symposium on Radioactively Tagged Organic Compounds ? A. K. Zille
Collaboration Notebook
CONFERENCES AND MEETINGS
All-Union Conference on Water Treatment in Nuclear Power Stations ? L. M. Voronin,
V. M. Gordina, and V. A. Mamet
International Conference on Elementary Interactions at Low Energies ? P. S. Isaev
International Conference on Horizons in Science 1976 ? V. I. Asvrin
Conference on the Production of Particles with New Quantum Numbers ? A. D. Dolgov
Symposium on Applications of 252C1 ? A. K. Shvetsov
Seminar on Computer Simulation of Radiation-Induced and Other Defects ? Yu. V. Trushin
Engl./Russ.
818
195
819
195
820
197
821
197
822
198
824
199
826
201 -
830
203
832
205
834
206
837
208
838
209
840
211
842
212
844
214
845
215
846
216
848
217
849
217
850
218
851
219
852
220
853
221
856
222
858
223
860
225
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Engl./Russ.
SCIENTIFIC AND TECHNICAL EXCHANGES
Visit of an ERDA Delegation to the USSR ? E F. Arifmetchikov
862
226
BOOK REVIEWS
Yu. A. Egorov, V. P. Mashkovich, Yu. V. Pankrat'ev, A. P. Suvorov, and S. G. Tsipin.
Radiation Safety and Nuclear Power Station Shielding ?Reviewed by N. G. Gusev. .
863
227
V. T. Tustanovskii. Accuracy and Sensitivity Estimation in Activation Analysis
? Reviewed by E. M. Filippov
864
227
G. Hammel and D. Okrent. Reactivity Coefficients in Large Fast-Neutron Power Reactors
(USA, 1970)?Reviewed by G. M. Pshakin
865
228
Volume 41, Number 4 October, 1976
ARTICLES
Problems of Radiation Safety in Nuclear Power Stations Containing VVE,R -440 Reactors
? L. M. Voronin, A. P. Volkov, and V. F. Kozlov
867
235
Monitoring the Reactivity of Extremely Subcritical Reactors by Means of Reactivity
Meters, Corrections Being Made to the Analog of the Source ? V. V. Bondarenko,
B. G. Dubovskii, R. E. Bagdasarov, V. A. Lititskii, and A. N. Efeshin
871
238
Continuous Analysis of Iodine, Cesium, Barium, Strontium, Yttrium, and Rare-Earth
Isotopes in the Aqueous Coolant of a Nuclear Reactor ? L. N. Moskvin,
L. K. Zakharov, G. G. Leont'ev, V. A. Mel'nikov, I. S. Orlenkov,
and G. K. Slutskii
874
241
Acceleration of Ions by the Quasi-Static Field of an Electron Beam ? A. N. Lebedev
and K. N. Pazin
878
244
Compensation of a Space-Limited Positive Charge by Electrons ? V. M. Kulygin
and V. I. Telegin
882
247
REVIEWS
Nuclear Reactions in the Sun ? N. A. Vlasov
887
251
Radiation Safety at Nuclear Power Stations ? N. G. Gusev
890
254
Radiation Safety during Operation of High-Intensity Radiation Equipment ? E. E. Chistov
897
260
The Relative Danger of Nuclear Power Stations (NPSs) and Thermal Power Stations (TPSs)
for the Environment ? Yu. V. Sivintsev and E. N. Teverovskii
901
263
DEPOSITED PAPERS
The Possibilities of Determining Copper Trichlorphenolate in Plants by the Neutron
Activation Method ? G. I. Gofen and A. A. Kist
905
268
Pulsed Electron Current Excited by y Radiation in Air ? A. V. Zhemerev,
Yu. A. Medvedev, and B. M. Stepanov
906
268
LETTERS
Rate of Change of Reactivity of the BOB -60 Reactor during the Operating Period
? V. A. Afanas'ev, V. N. Efimov, N. V. Krasnoyarov, N. N. Skulkin,
and R. E. Fedyakin
907
270
A Method of Determining the Thermophysical Properties of Reactor Materials at Elevated
Temperatures ? S. A. Balankin, D. M. Skorov, and V. A. Yartsev
909
271
Production of Intense Monochromatic Beams of Longwave Neutrons from the Open
Tangential Channel of a Nuclear Reactor ? B. N. Goshchitskii and V. G. Chudinov
912
273
Simplified Determination of the Number of Fission Neutrons Emitted Per Thermal Neutron
Absorbed in a Uranium?Water Lattice ? G. G. Bartolomei, V. D. Baibakov,
A. V. Klimenko, and V. D. Sidorenko
914
274
1132
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Engl./Russ.
Experience Gathered in the Utilization of Low-Energy Accelerators for the Activation
Analysis of Metallurgical Products ? L. V. Navalikhin; D. I. Blinkov,
and V. A. Muminov
917
277
Measurement of the Effective Resonance Integral of Thorium Metal ? L. N Yurova,
A. A. Polyakov, V. P. Rukhlo, and Yu. E. Titarenko
920
279
Calculation of 3-Particle Total Backscattering Coefficient for Thick Absorbers
? V. A. Kuz'minykh and S. A. Vorob'ev
922
280
Range of Fast Electrons in Dielectrics ?0. B. Evdokimov, B. A. Kononov,
and N. I. Yagushkin
924
282
COME CON CHRONICLES
Thirtieth Meeting of COMECON Standing Committee on the Peaceful Uses of Atomic
Energy ? Yu. I. Chikul
927
284
CONFERENCES, MEE TINGS, AND SEMINARS
Third All-Union Scientific and Practical Conference on Radiation Safety ? V. I. Ivanov
and U. Ya. Margulis928
284
All-Union Conference on the Use of Neutrons in Medicine ? B. A. Berdov ?
and V. N. Ivanov
930
286
Third Meeting of the TATE Technical Committee on High-Activity and a-Emitting Waste
? Yu. P. Martinov
932
287
5th International Symposium on the Desalination of Sea and Salt Water ? 0. I. Martynova
933
288
BOOK REVIEWS
V. I. Levin. Nuclear Physics and Nuclear Reactors ?Reviewed by V. K. Vikulov
934
292
B. M. Kogan, I. M. Nazarov, and Ski. D. Fridman. Principles of they Spectrometry of
Natural Media ? Reviewed by E. M. Filippov
935
293
V. A. Bobrov, F. P. Krendelev, and A. M. Hofman. The y-Spectrometric Analysis in
a Chamber with Low Background ? Reviewed by E. M. Filippov
936
293
A. S. Serdyukova and Yu. T. Kapitanov. The Isotopes of Radon and Its Decay Products in
Nature ? Reviewed by E. M. Filippov
937
294
Volume 41, Number 5 November, 1976
ARTICLES
A Computational Method of Approximating Discrete Measurements of the Power
Distribution in Power Reactors - I. Ya. Emel,yanov, V. V. Postnikov,
and G. B. Yurkin
939
299
Effect of Scale, Geometry, and Filler on the Strength of Steel Vessels to Tnternal
Pulsed Loads - V. I. Tsypkin, A. G. Ivanov, V. N. Mineev,
and A. T. Shitov
944
303
Heat-Resisting Austenitic steel with High Cscacking Resistance - N. E. Karskii,
I. P. Kul'ko, and V. S. Goryunova
950
309
Investigation of the Structure and Mechanical Properties of OKh16N15M3B Steel
Irradiated by Helium Ions - N. P. Agapova, I. N. Afrikanov, F. P. Butra,
I. V. Golikov, A. M. Kaptel'tsev, E. G. Mironova, V. D. Onufriev,
Yu. N. Sokurskii, and V. I. Chuev
955
314
The Effect of Nuclear Fuel Enrichment on the Formation of Transuranium Isotopes
in Power Reactors - T. S. Zaritskaya, A. K. Kruglov, and A. P. Rudik
963
321
Measurement of Spectrum y Radiation inside a Reactor - B. A. Briskman,
V. D. Bondarev, M. Z. Tarasko, and R. B. Novgorodtsev
967
325
K X-Ray Spectra of Fragments from the Fission of 235U by Fast Neutrons, and the
Energy Dependence of I) in the Heat-Balance Method - A. G. Donichkin,
A. N. Smirnov, and V. P. Eismont
972
329
1133
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Engl./Russ.
Measurement of the Spectrum of High-Energy Protons Emerging from the Shielding
of a 680-MeV Synchrocyclotron ? V. E. Aleinikov, V. P. Gerdt,
and G. N. Timoshenko
975
332
REVIEWS
Mass Distribution of Fission Products ? B. D. Kuz'minov
979
335
Experimental Investigation of a Decay of Actinoid Elements (Current state of Results
on a Decay) ? S. A. Baranov, A. G. Zelenkov, and V. M. Kulakov
987
342
DEPOSITED ARTICLES
Computing Analysis of the Temperature Pulsations in the Tube Wall of a Direct
Flow Boiler and Experimental Verification ? A. V. Nekrasov, S. A. Logvinov,
G. A. Volkov, V. V. Babykin, I. N. Testov, and V. P. Spasskov
993
349
Dose Distribution in Relation to Linear Energy Transfer for Various Forms of Ionizing
Radiation ? E. I. Nizhnik, Ya. I. Lavrentovich, and 0. P. Verkhgradskii
994
349
Determination of Cobalt Concentration in Stainless and Carbon Steels by the Activation
Method ? B. G. Gimel'shtein, P. V. Teplov, V. A. Fedorov,
and 0. P. Bol'shakov
995
350
Radiation Stability of Graphite with Homogeneous Structure ? Yu. S. Virgil'ev,
I. A. Kondrat'ev, V. G. Makarchenko, and I. M. Rozenman.
996
351
Determination of the Concentration of Bismuth from the a Activity of 2I0Po by Means of
Track Detectors ? B. P. Zverev, L. E. Krasivina, 0. G. Murtazin,
Yu. F. Simakhin, M. M. Aripov, and M. M. Usmanova
997
351
Gas-Discharge Ion Sources for Electromagnetic Mass Separator on a Heavy-Ion Beam
I. Ion Source Construction and Efficiency ? N. S. Ivanov, A. P. Kabachenko,
I. V. Kuznetsov, and N. I. Tarantin
998
352
Gas-Discharge Ion Sources for Electromagnetic Mass Separator on Heavy-Ion Beam
H. Operating Speed of Ion Source ? A. P. Kabachenko, I. V. Kuznetsov,
Li Hen Su, and N. I. Tarantin
999
353
LETTERS TO THE EDITOR
The Internal Power-Distribution Monitor System in the Reactors at the
Bilibino Nuclear Power Station ? L. G. And reev, B. G. Dubovskii,
V. A. Zagadkin, E. V. Koryagin, V. F. Lyubchenko, M. G. Mitel'man,
K. N. Mokhnatkin,G. P. Pochivalin, N. D. Rozenblyum,
G. E. Soldatov, and V. B. Sukhoverko
1001
354
Effect of Beryllium Impurity in Uranium Dioxide on the Error in Plutonium
Breeding Control ? V. I. Bulanenko and V. V. Frolov
1003
356
Distribution of the Neutron Importance Function in a Reactor with a Trap
? V. S. Bykovskii and M. N. Lantsov
1006
357
Measurement of Relative Probability of Electron Capture in 242A m Decay
? V. Ya. Gabeskipiya, A. P. Chetverikov, V. V. Gryzina,
and V. V. Tikhomirov
1008
359
Interrelation of Various Xenon Optimization Problems ? A. S. Gerasimov
and A. P. Rudik
1009
360
Measurement of Depth Dose Distributions from Beta Sources in Various Materials
? N. A. Komarov and G. B. Radzievskii
1012
362
Anisotropy of Electron Fluxes behind Extended Heterogeneities in a Material
? V. I. Boiko, V. V. Evstigneev, B. A. Kononov, A. L. Plotnikov,
and E. A. Gorbachev
1014
363
CONFERENCES AND MEETINGS
All-Union Scientific-Technical Seminar on "Experience in Designing, Constructing,
and Operating Atomic Power Plants" ? L. M. Voronin
1018
367
Soviet?American Meeting on Container Materials for Fuel Elements of Fast Reactors
? A. A. Proshkin
1019
367
1134
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All-Union Conference on the Chemistry of Transplutonium Elements ? A. M. Rozen
International Meeting of Experts on Uranium Ore Processing ? G. F. Ivanov
Soviet?French Seminar on Radio-Frequency Methods of Plasma Heating in Closed
Systems ? V. V. Alikaev
Engl./Russ.
1 021 369
1024 371
1026 373
Second All-Union Seminar on High-Energy Nuclear Physics ? V. F. Litv in
1 028
374
International Conference on the Interaction of Mesons with Nuclei
? Yu. A. Batusov
1 030
375
Seventh International Colliquium on Multiparticle Reactions ? I. M. Gramenitskii
and A. V. Efrimov
1032
377
Third International Conference on the Properties of Nuclei Far from the Stability
Line ? V. A. Karanukhov
1034
378
Volume 41, Number 6 December, 1976
ARTICLES
An Investigation of Resonance Absorption of Neutrons
in an RBMK-Type Grid ? L. N. Yuroba, A. V. Bushuev,
A. F. Kozhin, M. B. Egiazarov, and P. M. Kamanin
1 037
387
Two-Dimensional Kinetic Calculation of Nuclear Reactor
by the Finite-Elements Method ? N. V. Isaev, I. S. Slesarev,
N. E. Gorbatov, and A. P. Ivanov
1042
391
Start-up Tests on the Efficiency of the Biological Protection
on Nuclear Power Stations Equipped with Water-Moderated
Water-Cooled Power Reactors ? A. S. Iz'yurov, A. S. KuzhiP,
V. N. Mironov, A. I, Rymarenko, and S. G. Tsypin
1 046
395
An Experimental Study of the Way in Which the Internal Moderators
of Annular Fuel Elements Affect Resonance Absorption
in the Uranium ? I. M. Kisil', V. F. Lyubchenko, I. P. Markelov,
V. V. Orlov, V. V. Frolov, and V. N. Sharapov
1 051
399
Formation of Vacancy Micropores during Bombarding of Nickel
by Similar Ions with Energy up to 300 keV ? N. P. Agapova, I. N. Afrikanov,
V. G. Vladimirov, V. M. Gusev, V. D. Onufriev, and V. S. Tsyplenkov
1055
402
Effect of Reactor Radiation on the Susceptibility of Austenite Steel
to Intercrystallite Corrosion ? S. N. Votinov, Yu. I. Kazennov,
V. L. Bogoyavlenskii, V. S. Belokopytov, E. A, Krylov, L, M. Klestova,
and L. I. Reviznikov
1058
405
Coherent Beam Instability in the IFVE Accelerator
? V. I. Balbekov and K. F. Gertsev
1061
408
DEPOSITED ARTICLES
Multiorbit Induction Accelerators ? A. A. Zvontsov, V. A. Kas'yanov,
and V. L. Chakhlov
1 066
413
Pressure Change in a Vessel with Saturated Water on Being Unsealed
? A. V. Alferov, V. V. Fisenko, and A. D, Shcherban'
1067
413
Quantitative Estimates of the Energy of X-Ray Field Backscattered
from Air ? F. L. Gerchikov
1068
414
Computation of the Radiation Field of a Unidirectional Point Source
of Fast Electrons by the Monte Carlo Method
? A. V. Plyasheshnikov and A. M. Kol'chuzhkin
1069
415
Determination of Neutron Spectrum from Measurements with a Small
Number of Detectors ? G. M. Obaturov and A. A. Tumanov
1 070
416
Floating Control of a Power Reactor with Respect to a Parameter
with Time Lag ? B. G. Ogloblin and K. N. Prikot
1071
416
1135
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Engl./Russ.
LETTERS
Sputtering of Metallic Surface by Fission Fragments
- B. M. Aleksandrov, I. A. Baranov, N. V. Babadzhanyants,
A. S. Krivokhatskii, and V. V. Obnoskii
The Composition of the Radiolysis Products of the System
CO2-H20(D20)-Oil Formed in a KS-150 Reactor
- M. I. Ermolaev, A. K. Nesterova, and V. F. Kapitanov
Determining the Thermal Power Outputs of Small High-Temperature
Nuclear Power Plants - A. I. El'tsov, A. K. Zabavin,
Yu. A. Kotelinikov, A. A. Labut, E. P. Lana, I. P. Sviridenko,
and Yu. L. Shirokovskii
Influence of Irradiation on the Oxidation Kinetics of the Alloy
Zr +2.5% Nb - M. G. Golovachev, V. V. Klyushin,
and V. I.Perekhozhev
Influence of Boron on Radiation Embrittlement of Low-Alloy Steel
- V. A. Nikolaev and V. I. Badanin
Measurement of the Ratio o-f(239Pu)/o-f(235U) for Neutron Energies
of 0.27-9.85 MeV - E. F. Fomushkin, G. F. Novoselov,
Yu. I. Vinogradov, and V. V. Gavrilov
Nuclear y Resonance Method for Investigating EI-69 Austenite Steel
Irradiated with y Quanta or Fast Neutrons - I. M. V'yunnik,
P. 0. Voznyuk, and V. N. Dubinin
Effect of Temperature on the Porosity of Nickel Irradiated with Nickel Ions
-5, Ya. Lebedev and S. D. Panin
Numerical Y-Ray Albedo from Limited Sections of the Surface
of Reflecting Barriers - D. B. Pozdneev and M. A. Faddeev
Yields of 299T1, 201TI,
1 and 294T1 during Proton and Deuteron
Irradiation of Mercury - P. P. Dmitriev, G. A. Molin,
Z. P. Dmitrieva, and M. V. Panarin
Albedo of a Cylindrical Rod - V. V. Orlov and V. S. Shulepin
Operative Monitoring of Fission Products in Sodium Coolant of Fast Reactor
- V. B. Ivanov, V. I. Polyakov, Yu. V. Chechetkin,
and V. I. Shipilov
CONFERENCES AND MEETINGS
Regeneration of Fast-Reactor Fuel - A. F. Tsarenko
Meeting of Four Nuclear Data Centers - V. N. Manokhin
Meetings on the Compilation of Nuclear Data from Reactions
with Charged Particles and Data on the Structure of the Atomic Nucleus
- L. L. Sokolovskii
IAEA Symposium on the Design and Equipment of "Hot" Laboratories
- B. I. Ryabov
Second Seminar on Computer Simulation of Radiation and Other Defects
-Yu. V. Trushin
International Conference on "Ion-Exchange Theory and Practice"
- V. V. Yakshin
BOOK REVIEWS
A. M. Petroslyants. From the Scientic Quest to the Atomic Industry.
Contemporary Problems of Atomic Science and Engineering
in the USSR - Reviewed by Yu. I. Koryakin
V. A. Zuev and V. I. Lomov. Plutonium Hexafluoride
- Reviewed by N. P. Galkin
INDEX
Author Index, Volumes 40-41, 1976 ... ? ?
Tables of Contents, Volumes 40-41, 1976
1136
1072
417
1073
418
1076
420
1078
422
1080
422
1083
425
1085
427
1087
428
1089
430
1091
431
1094
434
1095
435
1097
438
1100
440
1101
441
1102
442
1104
443
1106
444
1108
446
1109
447
? ? ?
- ? ?
? ?
?
1113
1119
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Declassified and Approved For Release 2013/09/23: CIA-RDP10-02196R000700080005-5
engineering
science
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