SOVIET ATOMIC ENERGY - VOL. 34, NO. 1

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• Publication Date: July 1, 1973
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iiussiat; Original Vol234, No. 1, January, 1973
2 July, 1973
SATEAZ 34(1) 1-100 (1973)
SOVIET
ATOMIC
ENERGY
ATOMAAO 3HEPII4R
(ATOMNAYA iNERGIYA)
TRANSLATED FROM RUSSIAN
CONSULTANTS BUREAU, NEW YORK
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SOVIET
ATOMIC
ENERGY
Soviet Atomic Energy is a cover-to-cover translation of Atomnaya
Energiya, a publication of the Academy' of Sciences of the USSR.
An arrangement with Mezhdunarodnaya Kniga, the Soviet book
export agency, makes available both advance copies of the Rus-
sian journal and original glossy photographs and artwork. This
serves to decrease the necessary time lag between publication
Of the original and publication of the translation and helps to im-
prove the quality of the latter. The translation began with the first
issue of the Russian journal.
Editorial Board of Atomnaya Energiya:
? Editor: M. D. Millionshchikov
Deputy Director
I. V. Kurchatov Institute of Atomic Energy
Academy of Sciences of the USSR \
Moscow, USSR
Associate Editors: N. A. Kolokol'tsov
N. A. Vlasov
A. A. Bochvar
N. A. Dollezhal'
V. S. Fursov
I..N. Golovin
V. F. Kalinin
A. K. Krasin
A. I. Leipuhskii
A. P. Zefirov
V. V. Matveev
M. G. Meshcheryakov
. P. N. Palei
V. B. Shevchenko
D. L. Simonenko.
V. I. Smirnov
A. P. Vinogradov
CopyrightC1973 Consultants Bureau, New York, a division of Plenum Publishing
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SOVIET ATOMIC ENERGY
A translation of Atomnaya Energiya
July, 1973
Volume 34, Number 1 January, 1973
ARTICLES
Some Characteristics of the Relationship between Uranium ?Molybdenum Mineralization
CONTENTS
Engl./Russ.
and Volcanogenic Formations ? V. M. Konstantinov and D. I. Yakunin
1
3
BIBLIOGRAPHY
New Books ? A. M. Petros'yants
4
6
ARTICLES
Dosimetry of y and Neutron Radiation with a Scintillation Spectrometer
? V. P. Kovalev, S. P. Kapchigashev, and L. P. Pavlov
13
7
Characteristics of the Personnel Neutron Track Dosimeter DINA
? I. S. Keirim-Markus, T. V. Koroleva, S. N. Kraitor, and L. N. Uspenskii
18
11
Activation of the Water Cooling Synchrocyclotron Components ? M. M. Komochkov
and Yu. G. Teterev
23
17
Modeling Nuclear Reactions in an Isotropically Irradiated Thick Target
? A. K. Lavrukhina, G. K. Ustinova, V. V. Malyshev, and L. M. Satarova
29
23
ABSTRACTS
Uranium in Carbonate Hydrothermal Solutions ? R. P. Rafal'skii
36
29
Threshold Instability of a Reactor with Respect to the Onset of Spatial Xenon
Oscillations ? V. N. Semenov
37
30
Experimental Investigation of Single-Stage Control Circuit of Coolant Outlet
Temperature in the BOR-60 Reactor ? V. A. Afana.s'ev, V. M. Gryazev,
and V. N. Efimov
38
30
Reliability of Radiochemical Plants with y -Radiation Sources ? Yu. D. Kozlov
and L. G. Filaretova
39
31
Embrittlement of Low-Alloyed Steels Caused by Neutron Irradiation in Water at
Temperatures below 100?C ? N. N. Alekseenko and V. A. Nikolaev
40
32
A 'y-Ray and X-Ray Detector Using Integration and Counting ? K. M. Kudelin,
L. Ya. Zabrodskaya, and V. P. Odintsov
y-Radiation Field over an Infinite Plane Source Separated by an Inactive Strip
? D. P. Osanov, M. Yu. Tissen, and V. G. Ryadov
42
42
33
33
Semiconductor a-Spectrometer for Analysis ? S. M. Solov'ev, A. N. Smirnov,
and V. P. Eismont
43
34
Spatial Distribution of Ionization Intensity near Radioisotopic Neutralizers of Static
Electricity ? A. S. Rozenkrantz
44
35
Neutron Activation Determination of the Content of Oxygen and Fluorine in Samples of
Zirconium and Tantalum ? V. I. Melentlev, V. V. Ovechkin, and V. S. Rudenko
45
35
Experimental Investigations of Modular or Sectional Concrete Biological Shielding
? V. B. Dubrovskii, V. N. Ivanov, and I. N. Martem'yanov
46
36
Passage of Radiations through Joints in Modular Concrete Shielding
? V. B. Dubrovskii and V. N. Ivanov
47
36
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Estimation of Dimensional-Weight and Energy Characteristics of Electron Accelerators
for Experimental and Industrial Radiation Installations ? V. S. Karmaza,
CONTENTS
(continued)
Engl./Russ.
I. F. ?Malyshev, and I. A. Prudnikov
48
37
LETTERS TO THE EDITOR
Leaktightness Monitoring of the Primary Loop in Steam Generators at Nuclear Power
Stations Using Water-Moderated Water-Cooled Power Reactor
? T. K. Fedchenko and A. A. Il'khman.
49
39
Fuel-Element Testing Channel Loop with Natural Coolant Circulation ? G. A. Klochko,
V. A. Kurov, V. I. Maksimenko, A. D. Martynov, V. G. Potolovskii,
M. G. Bul'kanov, and V. M. Selivanov
52
40
, Equation of State of UF 6 for Densities up to 0.01180 gicm3 and Temperatures up to 367?K
? V. V. Malyshev
55
42
Some Dosimetric Monitoring Results at the ITR-2000 Nuclear Reactor in Sofia
? I. T. Mishev and M. G. Gelev
57
44
Possible Suppression of a Plasma Cyclotron Instability by Electron Beam Modulation
? A. N. Karkhov
60
46
Buildup Factors of Scattered y-Radiation from a Point Source in an Unbounded Air
Medium ? M. N. Vrubell, S. N. Sidneva, and A. S. Strelkov
63
47
Use of Pa231 and U236 in Measuring Fast Neutron Spectra ? K. K. Koshaeva
and S. N. Kraitor
66
49
Asymmetry of the Photofission of Np237 as a Function of the Maximum Bremsstrahlung
Energy ? M. Ya. Kondrat'ko, V. N. Korinets, and K. A. Petrzhak........ .... . .
69
52
7-Activation Analysis of Carbon in Thorium and Uranium ? AF. Gorenko,
N. A. Skakun, G. M. Shevchenko, A. S. Zadvornyi, N. I. Bugaeva,
and A. P. Klyucharev
71
53
Linear Resonance Accelerator with a Steady Electron Flux ? B. A. Snedkov
and B. A. Turenko
74
55
Commissioning of Linear Accelerator Section in High-Frequency Quadrupole Focusing
? S. A. ll'evskii, I. M. Kapchinskii, G. F. Kuznetsov, A. P. Mallsev,
K. G. Mirzoev, V. V. Nizhegorodtsev, V. B. Stepanov, V. A. Teplyakov,
M. A. Kholodenko, and I. M. Sharashov
77
56
COME CON NEWS
Conference on Deactivation of Radioactive Wastes ? V. V. Kulichenko and N. A. Rakov.
80
59
Collaboration Logbook
83
60
INFORMATION: CONFERENCES AND SYMPOSIA
The IAEA Symposium on Burial of Radioactive Wastes ? B. S. Kolychev
86
62
The Fifth European Conference on Controlled Thermonuclear Fusion and Plasma
Physics ? V. A. Chuyanov
88
63
The International Conference on the Study of Nuclear Structure by Means of Neutrons
? V. I. Lushchikov
92
66
The Fourth All-Union Symposium on the Use of Stable Isotopes in Geochemistry
? S. F. Karpenko
95
67
BOOK REVIEWS
J. Hamilton and J. Manthuruthil (editors). Radioactivity in Nuclear Spectroscopy.
Modern Techniques and Applications ? Reviewed by N. A. Vlasov
98
70
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CONTENTS
(continued)
Engl./Russ.
D. De Soets, R. Gijbels, and J. Hoste. Neutron Activation Analysis ? Reviewed by
K. A. Baskova 99 71
Yu. I. Gal'perin, L. S. Gorn, and B. I. Khazanov. Measurements of Radiations in the
Cosmos ? Reviewed by V. V. Matveev 100 71
The Russian press date (podpisano k pechati) of this issue was 1/3/1973.
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
SOME CHARACTERISTICS OF THE RELATIONSHIP
BETWEEN URANIUM?MOLYBDENUM
MINERALIZATION AND VOLCANOGENIC FORMATIONS
V. M. Konstantinov and D. I. Yakunin UDC 550.42:553.495
Recent years have seen the publication of a number of papers relating to hydrothermal uranium sites
with a considerable amount of molybdenum in the ores; the ores separate out into a uranium?molybdenum
formation. A special characteristic of these ore sites is the fact that they are confined to regions charac-
terized by the development of volcanic-intrusive magmatic complexes. Many years investigations have
led to the authors to the conclusion that the relationship between the sites of the uranium?molybdenum
formations and the magmatogenic formations is different in regions with a different history of geological
development. In this paper we shall present some data as to the relationship between mineralization and
magmatogenic formations in two particular regions, and on the basis of these data we shall refine the
criteria defining the conditions governing the disposition of the ore sites.
One of the regions belongs to the framework of a median massif and the other to a Caledonian geosyn-
clinal area. The deposits of both regions are characterized by similarity of mineral composition; both are
confined to extrusive formations folded with acid rocks, or to their contacts with effusive-sedimentary or
metamorphic formations. However, the histories of the geological development of the regions contain
certain differences, an analysis of which enables us to gain a better understanding of the relation between
hydrothermal uranium?molybdenum mineralization and magmatism, and to estimate their potentialities
anew.
The first region is characterized by the following features of development. In the period completing
the geosynclinal stage, batholite-like granitoid intrusions were formed, accompanied by finer intrusive
regions and dikes represented by rocks of predominantly acid composition. In the orogenic period sub-
volcanic intrusions and multiple effusions of acid lavas penetrated the system and extrusive regions were
formed. At the same time the intrusion of dikes of medium composition occurred. The uranium content of
the intrusive and volcanogenic rocks exceeded the Clark values by a factor of several times.
The formation of granitoid intrusive masses was accompanied by quartz?albite metasomatosis,
appearing predominantly in gneiss?shales of the proterozoic age. Fine ore manifestations of uranium with
uranium pitch were confined to the metasomatites. The uranium mineralization was created after the
formation of the metasomatites and was close to them in time.
The principal uranium ore deposits lie in rocks subjected to intensive quartz?sericite metasomatosis
associated with the post-volcanic activity of the orogenic period. The time of ore formation is close to the
period of formation of the metasomatites.
The ore manifestations of the uranium?molybdenum formation are situated directly in the rocks of
the crater facies of paleo-volcanoes (felsites and quartz porphyries), or gravitate toward the contacts of
the extrusive beds with surrounding rocks. There is a relationship between the structure of the paleo-
volcanic masses and the disposition of the uranium ore manifestations. This relationship lies in the fact
that, for a low degree of crystallinity of the rocks of the crater facies, in those cases in which they are
represented by felsites, the ore beds are situated primarily in the craters. For a higher degree of crystal-
linity, when the craters are filled with quartz porphyries, the ore beds lie mainly at their contacts with the
surrounding rocks. Considerably more rarely the craters are filled with leucocratic granite porphyries;
Translated from Atomnaya Energiya, Vol. 34, No. 1, pp. 3-5, January, 1973. Original article
submitted March 3, 1972.
C 1973 Consultants Bureau, a division of Plenum Publishing Corporation, 227 West 17th Street, New York,
N. Y. 10011. All rights reserved. This article cannot be reproduced for any purpose whatsoever without
permission of the publisher. A copy of this article is available from the publisher for $15.00.
1
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\ /
Zone of ore
deposit
Region of overheating and
introduction of metals from
the magma
?
?1 s., ?2 +++f+
-4
Fig. 1 Scheme for the formation of ore-forming hydrothermal solu-
tions: 1) felsites; 2) quartz porphyries; 3) graphite porphyries; 4)
bed rocks.
in these cases the ore manifestations lie in the surrounding rocks at a certain distance from the contacts
with the graphite porphyries.
This relationship may be explained [1] by the scheme representing the creation of ore-forming hydro-
thermal solutions illustrated in Fig. 1. In explaining the scheme we must remember the following: 1)
around the cooling magmatic melt there existed a region of superheated rocks through which the gas-hydro-
thermal distillates passed from the magma, and in which no ores were formed; 2) when the distillates
reached a region of comparatively low temperature, unloading and ore-deposition took place.
We see from the scheme that the region of ore deposition lay at a certain distance from the radical
part of the paleo-volcanic system. Clearly, depending on the level of the contemporary erosive shear,
this region will be established either in the felsites (minimum erosive shear), or close to the contact of
the quartz porphyries (medium erosive shear), or in the metamorphic rocks (maximum erosive shear).
Thus the relationship between the disposition of the uranium ore manifestations and the degree of crystal-
linity of the crater facies may be explained by the time proximity between the processes of crystallization
and cooling of the magmatic melt in the radical parts of the paleo-volcanoes, on the one hand, and the
processes of ore-formation on the other.
Detailed studies of the uranium distribution in volcanogenic rocks [2] show that the uranium content
in the beds of felsites is three or four times greater than in the granite prophyries. This aspect of the
uranium distribution in rocks formed from a single magmatic melt may be explained by the transfer of
uranium from the magmatic melt during the formation of the deepest parts of the paleo-volcanic systems.
It follows from the foregoing data that, in the region under consideration, ore formation takes place
in two stages. The slight ore aggregates created after the formation of the batholite-like granitoid massifs
are controlled by the regions of development of quartz?albite metasomatites. The second stage of ore
formation took place in the period of the completion of magmatic activity. The uranium distribution charac-
teristics in the rocks and the spatial relationship between the ore manifestations and extrusive beds, and
also the nearness in time of formation of the mineralizations and volcanogenic rocks, indicate a genetic
relationship between the mineralization of the second stage and volcanism. On this basis, regions promis-
ing from the point of view of finding sites of uranium ?molybdenum formations are determined by the
presence of extrusive acid rocks and adjacent areas in which pre-ore quartz?sericite metasomatosis has
occurred.
The second region, which lies in a geosynclinical block within a fold region, is characterized by a
different history of its development in the concluding stages of formation.
In the geosynclinal period, subvolcanic intrusions of granodioritic and dioritic compositions were
formed. After the establishment of these, intensive volcanic activity occurred, revealing itself in multiple
volcanic eruptions, which led to the formation of thick beds folded with liparitic lavas and tuffs, and also
2
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necks of rhyolitic porphyries lying among effusive rocks. The volcanic period of magmatic activity was
completed by the formation of a subvolcanic mass folded with quartz porphyries and granite porphyries.
Volcanism was accompanied by the formation of low-temperature quartz?sericite metasomatites
which exhibited an increase in uranium content and individual points of uranium mineralization. No sub-
stantial segregations of uranium were established.
After the creation of the volcanogenic formations, there was an intrusion of large intrusive masses
folded with granitoids. The magmatic activity ended with the formation of dike rocks of medium composi-
tion.
The final stage in the magmatic activity was accompanied by the formation of quartz?albitic meta-
somatites in the most crumbling parts. Such parts include necks, folded massifs, severely crumbling
rhyolitic porphyries, contacts of dikes with effusive rocks, effusive liparitic porphyries, and ignimbrites.
The ore beds are chiefly confined to necks folded with rhyolitic porphyries. We also encounter ore
beds and fields confined to series of effusive rocks and controlled by faults, contacts with dikes, and
certain facial varieties of liparitic lavas. In all known fields the ore beds are confined to zones of inten-
sive quartz?albitic metasomatosis. According to absolute age determinations, nasturan was formed in the
post-granitic period.
The data relating to the region under consideration leads us to conclude that the ore-bearing thermal
springs and volcano-intrusive rocks are related paragenetically by the common nature of their magmatic
center. The fact that the majority of sites are confined to paleo-volcanic structures (necks of rhyolitic
porphyries) is due to the fact that these provide favorable structural?lithological conditions for the siting
of uranium mineralization. On this basis, we may consider promising regions to be those which contain
favorable structures and areas exhibiting intensive post-granite quartz?albite metasomatosis. Regions of
ore location favorable as regards lithological?structural conditions may be disposed, not only around necks
of rhyolitic porphyries, but also among beds of effusive rocks. It is quite probable that the fact that the
majority of fields of this type are found in necks rather than in effusive beds may be attributed to the com-
plexity involved in revealing the latter, since the ore beds of such fields may be controlled by oblique
structures, and are not always detected on the surface.
A comparative analysis of the uranium?molybdenum fields shows that in both regions their formation
took place after the completion of the magmatic activity, in connection with the quartz?albite and quartz
?sericite metasomatosis of the rocks. In the first region the uranium ore beds lie in quartz?sericite
metasomatites formed after the completion of the magmatic activity. Only small quantities of uranium are
here associated with the quartz?albite metasomatites. In the second region, on the other hand, the uranium
ore beds are disposed mainly in the quartz?albite metasomatites, whereas only small segregations of
uranium are located in the quartz?sericite metasomatites.
In both regions the sites gravitate toward the extrusive formations. In the first region this is due to
the arrival of ore-bearing thermal springs from the volcanic chambers; hence this spatial confinement,
in combination with intensive quartz?sericite metasomatosis, is a reliable prospecting criterion. In the
second region the confinement of the ore manifestations to extrusive formations is explained by exclusively
structural?lithological factors. In this case the control of ore manifestations by necks may this be con-
sidered as a particular case of the manifestation of one of the prospecting criteria. In more general form
this criterion specifies the confinement of uranium?molybdenum ore manifestations to places in which
favorable structures develop (necks, faults, dikes, etc.).
LITERATURE CITED
1. M. M. Konstantinov, Izv.,Akad. Nauk SSSR, Ser. Geol. , No. 1, 95 (1962).
2. V. M. Konstantinov, At. Energ. , 22, No. 5, 416 (1967).
3
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BIBLIOGRAPHY
NEW BOOKS
A. M. Petros'yants
I. N. Golovin and I. V. Kurchatov. From Scientific
Research to Atomic Industry, Modern Problems of
Atomic Science and Engineering in the USSR. 2nd
Edition. Atomizdat, Moscow, 1972 t
Thousands of Soviet people have worked side by side, during the post-war years, with the late Aca-
demician Igor' Vasil'evich Kurchatov, who was mandated by the party and the government to head work on
atomic science and engineering in the socialist fatherland.
This book (the first edition of which came out in 1967) tells of the life and deeds of this remarkable
scientist, full of the joy of life, a responsive and sympathetic individual, noted for his exacting demands
on himself as on others, a leading public activist, communist, fighter for peace and for collaboration
between the peoples, three times Hero of Socialist Labor, a recipient of the Lenin Prize and State Prizes,
and even while still living a full-fledged national hero of our people.
* * *
F. Ya. Ovchinnikov, L. M. Voronin, L. M. Golubev,
et al. Operation of the Reactor Installations at the
Novaya Voronezh' Nuclear Electric Power Stations.
Atomizdat, Moscow, 1972
Experience in the operation of the reactor installations at the Novaya Voronezh' nuclear-fueled elec-
tric power generating station, using water-cooled water-moderated power reactor types, has been re-
viewed and widely disseminated in the USSR and in the COMECON member-nations. This text offers a
concise presentation of the operating principles of water-cooled water-moderated power reactors, basic
characteristics and a description of the reactors in service at the Novaya Voronezh' nuclear power station,
radiation monitoring and emergency protection systems, and analyzes the performance of the basic equip-
ment and process flowsheets. Close attention is given to the selection of fuel loadings and to examination
of the basic characteristics of the reactor cores, to the operating conditions of the reactor units, and to
topics involving nuclear and radiation safety, monitoring of the state of the metal in the process equipment,
and piping, decontamination, and inspection and overhaul of power equipment.
The book will be useful to specialists working in the design, installation, and adjustment of nuclear
power stations, and also to students majoring in power engineering, heat transfer, and engineering physics.
* * *
t See review in Atomnaya Energiya, Vol. 33, No. 6 (1972).
Translated from Atomnaya Energiya, Vol. 34, No. 1, pp. 6, 16, 38, 69, 70, January, 1973.
C 1973 Consultants Bureau, a division of Plenum Publishing Corporation, 227 West 17th Street, New York,
N. Y. 10011. All rights reserved. This article cannot be reproduced for any purpose whatsoever without
permission of the publisher. A copy of this article is available from the publisher for $15.00.
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I . A. Arshipov, G. A. Vasil' ev, Yu. A. Egorov,
et al. Serpentinite Concrete for Shielding of
Nuclear Reactors, Yu. A. Egorov (Editor).
Atomizdat, Moscow, 1972
Physicomechanical, heat-transfer, thermal, vibrational, shielding, and other relevant properties
of serpentinite concrete responsible for the great popularity of that material in reactor design and con-
struction are described. Constants and procedures for design calculations of serpentinite shielding are
cited. Topics concerning the fabrication and laying of concrete in the construction of shielding are dis-
cussed.
The text can be used as a reference manual by engineers and designers concerned with nuclear re-
actor shielding problems.
* * *
L. R. Kimel' and V. P. Mashkovich. Protection
against Ionizing Radiations, Reference Handbook,
2nd Edition. Atomizdat, Moscow, 1972
This manual contains all necessary data for design calculations of protection and shielding installa-
tions needed for work where radioactive materials are handled. Measurement units are presented, with
some information pertaining to ionizing radiations, the principal characteristics of radiation sources,
limiting permissible radiation levels, and so forth. Information is provided on protection against T-radia-
tions, neutrons, a- and 0 -radiations, and x-rays. Passage of radiation through inhomogeneities in shield-
ing is discussed.
The second edition of the handbook has been extensively revised and enlarged. Solutions of specific
problems are provided as examples in the treatment of the most difficult sections. The handbook is sup-
plemented with new tabular functions.
The book is written for engineers and physicists, research workers, graduate students, and under-
graduates, and also for a wide range of persons concerned with shielding and protection against radiations
in work where sources of ionizing radiations and radioactive materials are handled.
* * *
B. V. Nemirovskii, A. P. Serzhantov, and V. V. Shipulin.
Operation and Maintenance of Equipment for Measurements
of Ionizing Radiations, No. 2, Radiometers. Atomizdat,
Moscow, 1972
Radiometric instruments are employed to monitor the radiation environment in different rooms
exposed to radiations, to monitor the extent of contamination of surfaces of special clothing and protective
overalls worn by personnel, and also to monitor radiation exposure of the skin of personnel, to take
readings on the concentration of radioactive gases and aerosols in air and of radioactive substances in
liquid, and to monitor the activity of preparations and minerals. Reference data are provided in the text
on radiation monitoring instruments, on conditions and rules governing their proper use, typical designs
and arrangements, adjustments, care and maintenance.
The book is written for workers and technicians engaged in services responsible for inspection,
maintenance, and repair of radiometric instrumentation.
* * *
5
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V. P. Volodin, B. A. Korotin, and E. A. Ryabova.
Operation and Maintenance of Equipment for
Measurements of Ionizing Radiations, No. 3,
Dosimeters. Atomizdat, Moscow, 1972
Reference data are cited on the characteristics of the principal modes of ionizing radiations and their
interactions with matter, the basic concepts of the dosimetry of ionizing radiations, terms, formulas, and
relationships relating the characteristics of ionizing radiations to dose level, the specific requirements
applicable to instruments measuring dose level and dose rate of ionizing radiations. Conditions and rules
for handling and operating dosimeters of ionizing radiations, inspection, checkout, and calibration of such
dosimeters, and verification of their basic performance parameters at repair and maintenance workshops,
are described. Rules governing adjustment and repair, and the requisite inspection and measurement
equipment, are covered in detail for each type of dosimeter.
The text is written for technicians in dosimetric service, and also for specialists dealing with radia-
tion measurements.
* * *
V. P. Volodin, B. A. Korotkin, and A. M. Radyvanyuk.
Operation and Maintenance of Equipment for
Measurements of Ionizing Radiations, No. 4, Detection
Units for Ionizing Radiations. Atomizdat, Moscow,
1972
Reference data are cited on the characteristics of the principal modes of ionizing radiations and their
interactions with matter, on detectors, photomultipliers, and units for detecting ionizing radiation. Condi-
tions and rules and regulations governing the use of detection units based on different design principles
are presented. Standard designs and layouts of detection systems, their functions and operating principles,
basic performance parameters, and the functions of subassemblies and subsystems, wiring diagrams for
radiation detectors, and the effect of circuit design on the characteristics of the detection units, are among
the topics discussed. Rules governing the adjustment and maintenance of detection units and of each in-
dividual functional subsystem are covered in detail.
* * *
A. A. Kurashov. Identification of Pulses from
Radiation Detectors, Atomizdat, Moscow, 1972
Methods and specific circuitry needed in the identification and separate recording or analysis of
pulses from detectors in the case of different species of charged particles are discussed. Attention is
centered on techniques used in experimental intermediate-energy physics. A large section of the book is
devoted to the methods and arrangements for separating pulses by shape that is now quite popular in
neutron spectrometry. Electronic circuitry for gas, scintillation, and semiconductor detectors is discus-
sed. Criteria for evaluating the performance of such circuits and arrangements, and recommendations
on the best ways to inspect them and study their characteristics, are cited. Problems encountered in
recording rare events against a considerable background of accompanying and masking radiations are
discussed.
The book is written for a wide range of scientists, engineers, and technicians specializing in experi-
mental physics. It will also be useful to graduate students and senior undergraduates majoring in elec-
tronics and physics.
6
* * *
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Declassified and Approved For Release 2013/09/15: CIA-RDP10-02196R000400010001-9
R. D. Vasil'ev. Fundamentals of the Metrology
of Neutron Radiations. Atomizdat, Moscow,
1972
The scientific fundamentals of the metrology of neutron measurements are laid down. Compatibility
between the results of neutron measurements taken with the aid of different techniques and types of equip-
ment is discussed. Methods of direct, indirect, and combined measurements of physical variables char-
acterizing the neutron fields of nuclear reactors, accelerators, and isotope sources are reviewed. Ways
of pinpointing, handling, and eliminating systematic errors and bias are analyzed.
Techniques for mutual comparisons of measures and measuring instruments are reviewed system-
atically. The problem of metrological backup and servicing of neutron measurements is analyzed in
detail. Close attention is given to terminology. Pathways of development of the metrology of neutron
radiations are outlined, and the principal problems are formulated.
The monograph is written for engineers, scientists, graduate and undergraduate college students
specializing in nuclear physics and applied subdivisions, and also for workers in other realms of science
whose activities call for ability to deal with neutron measurements.
* * *
N. M. Sinev and P. M. Udovichenko. Packless
Water Pumps, 2nd Edition. Atomizdat, Moscow,
1972
The specific features of the design and calculations of packless canned centrifugal water pumps,
zero-leakage pumps, used in the nuclear power industry are presented. Special attention is given to
bearing supports using "water lubrication," and to calculations of the forces acting on them, as well as
to the thin-walled baffle providing a pressuretight enclosure for the stator of the electric drive motor, and
the conditions governing reliable pump performance.
Information is provided on the design of circulation type canned pumps on stream at the Novaya
Voronezh' nuclear power station and the Belyi Yar nuclear power station, on board the icebreaker Lenin,
and at various foreign nuclear power stations.
A large section in the book is devoted to packless pumps with mechanical shaft seals, i.e., to pumps
featuring limited or controlled leakage.
The book is written for power engineers and for heat-transfer engineers, for designers and operators
of nuclear power plants and nuclear power-generating stations. It would also be useful as a training aid
for instructors and students specializing in machinery design, heat transfer, and power engineering.
* * *
F. P. Denisov and V. N. Mekhedov. Nuclear Reactions
at High Energies. Atomizdat, Moscow, 1972
Results of theoretical and experimental research findings on high-energy nuclear reactions amassed
over the past two decades are discussed in this text. The model of direct interaction is subjected to
detailed discussion in its quantum-mechanical and classical variants (impulse approximation with distorted
waves), as well as the intranuclear cascade model, and experimental data obtained by techniques involving
photographic plates, radiation counters, and radiochemistry are discussed.
The book does not require any special theoretical background of the reader, and may be useful not
only to experimental physicists, but also to engineers and radiochemists working on methodological and
applied problems in high-energy nuclear physics.
* * *
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Declassified and Approved For Release 2013/09/15: CIA-RDP10-02196R000400010001-9
V. S. Barashenkov and V. D. Toneev. Interaction
of High-Energy Particles and Nuclei with Nuclei.
Atomizdat, 1972
The text dealswith a domain of high-energy physics that is of major importance and that is undergoing
rapid development: strong interactions of particles and nuclei ? nuclear processes at high energies with
treatment of the most recent achievements and trends in the development of the theory accounting for those
processes (the optical model, and Glauber elastic-scattering theory, stochastic treatment of all aspects of
intranuclear cascades, etc.).
The book will be of interest to specialists working in the field of nuclear physics and physics of
elementary particles, as well as of great benefit to specialists concerned with radiation shielding of space-
ships, the study of the biological effects of penetrating radiations, or the design of high-current accelera-
tors.
L. L. Kunin, E. D. Malikova, and B. A. Chapyzhnikov.
Determinations of Oxygen, Carbon, Nitrogen, and
Hydrogen in Alkali Metals and Alkali Earths.
Atomizdat, Moscow, 1972
Alkali metals and alkali earths have met with broad applications as coolants in nuclear power prac-
tice. The purity of the metal, particularly freedom from gaseous impurities, is of paramount importance
in these applications.
The physicochemical fundamentals of the techniques for making oxygen, carbon, nitrogen, and
hydrogen determinations in alkali metals and alkali earths are explained. Close attention is given to de-
termination of different forms in which gaseous impurities may be present in metals. Techniques for
taking representative samples from a melt, and the equipment employed in analytical inspection of samples,
are described. Specific analytical procedures developed in the USSR and elsewhere are covered.
The book is intended for a wide range of analytical chemists engaged in analytical control work in
the metallurgical and chemical process industries, and also those engaged in the nuclear power industry,
in electronics, in aerospace, etc.
* * *
Yu. P. Belyaev. Applications of Radioactive
Tracers to Metallurgical Process Research.
Atomizdat, Moscow, 1972
Applications of radioactive tracers in metallurgical processes are described. The necessary in-
formation on the physicochemical fundamentals of the method, and techniques of practical applications of
tracers, are cited. Particular examples of the use of radioactive tracers. for research on blast-furnace,
open-hearth, and converter production processes, as well as research on the crystallization processes of
large-size slabs to be rolled into sheet. Special attention is reserved for mass transfer in molten steel
in various metallurgical production facilities, when ingots of killed steel and rimmed steel solidify.
The book is written for engineers and technicians employed in scientific-research organizations and
metallurgical plants, also for graduate and undergraduate students majoring in radioisotope techniques
and in the theory of metallurgical processes.
* * *
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I. M. Lipova. Nature of Metamictic Zircons.
Atomizdat, Moscow, 1972
This book is devoted to metamixy, one of the urgent problems in mineralogy. Original results from
an all-sided investigation of the series of zircons, which constitute a unique series, from crystalline to
x-ray-amorphous differences, are reviewed. A detailed study carried out on an extensive and systemat-
ically selected collection of samples taken from different types of occurrences in the USSR and in other
countries made it possible to present a complete picture of the nature of metamictic zircons. The research
findings show that the metamictic state of the mineral is due primarily to the effects of ionizing radiations
of uranium and thorium incorporated in the composition of the mineral.
The book is written for mineralogists, crystal chemists, and crystal physicists.
* * *
G. A. Krestov. Thermochemistry of Compounds
of Rare-Earth and Actinoid Elements. Atomizdat,
Moscow, 1972
The use of thermodynamical characteristics to determine various properties of ions and compounds
of all the rare-earth and actinoid elements is discussed in this monograph from the vantage points of
currently held concepts. The new standard states for ions in the gaseous state and in solution introduced
by the author are used in the text. A systematic analysis of the dependence of interionic distances and
crystal?chemical radii of ions on the temperature is carried out. Many unknown properties of the ions
and compounds of rare-earth actinoid elements are determined at different temperatures. Modern view-
points on solvation of ions, the structure of water and ionic solutions are discussed. The thermodynamical
characteristics of structural changes in water in response to hydration of ions of rare-earth and actinoid
elements are introduced, and also in response to dissolution of the compounds in water.
' The text may be a useful aid to research workers, engineers, instructors, graduate students, and
senior undergraduates.
* * *
V. L. Barsukov, G. D. Gladyshev, V. N. Kozyrev,
et al. Conditions Governing the Formation of
Uranium Occurrences in Volcanic Depressions,
Edited by Corresponding Member of the USSR
Academy of Sciences A. I. Tugarinov. Atomizdat,
Moscow, 1972
Conditions governing the formation of uranium occurrences in volcanic depressions typical of many
ore provinces in Eurasia and America are discussed in the text. It is demonstrated that the solutions
circulating within the confines of the depressions play an important role in ore formation, often showing
an acidic reaction, and containing appreciably high concentrations of sulfates, chlorides, and carbonates.
Attention is focused on physicochemical analysis of interactions between ore-bearing solutions with
effusive-sedimentary rocks in the depression, and the changes they bring about in the composition of the
rocks and solutions. It is established that this interaction is the principal reason for the deposition of
uranium and the components accompanying it.
The book is written for a broad readership of geologists, working either in production or at scientific
research institutes. It will also be useful to students at graduate or undergraduate level specializing in
economic geology.
* * *
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Yu. A. Shukolyukov and L. K. Levskii.. Geochemistry
and Cosmochemistry of Isotopes of the Noble Gases.
Atomizdat, Moscow, 1972
This text is the first review literature on the geochemistry and space chemistry of isotopes of the
noble gases. Nuclear reactions leading to the formation of isotopes of the noble gases in the lithosphere,
isotope anomalies in various media, migration of isotope gases through the lithosphere, hydrosphere, and
atmosphere are discussed. Concepts relating to the history of isotopes of the noble gases in the evolution
of the lithosphere, hydrosphere, and atmosphere of the earth are put forth. Light is shed on the present
status of the problem of the cosmochemistry of isotopes of the noble gases, with attention given to their
cosmogenic, radiogenetic, and primary isotopes contained in meteoritic matter and in lunar matter.
Possibilities of utilizing isotopes of the noble gases in the solution of various problems in cosmology are
explored.
The book is intended for research geochemists, radiochemists, geologists, physicists, and also for
instructors, graduate students, and senior undergraduates in the appropriate specialties.
* * *
J. Matthews and R. Walker. Mathematical Methods
in Physics (translated from the English). Atomizdat,
Moscow, 1972
This book comprises a lecture course given by R. Feynmann at the California Institute of Technology.
Most of the standard topics in mathematical physics are discussed in the text in an unusual and novel manner.
Normal oscillations of certain symmetric configurations are analyzed by the methods of group theory, there
is a diagrammatic decomposition of the Fredholm solution of linear integral equations, dispersion relations
and related integral equations are discussed, and, finally, there is a detailed discussion of applications of
the theory of probabilities to processing of experimental data.
The book can be used by student majors in physics as a textbook on methods of mathematical physics,
and can also be useful to scientists and students studying these topics on their own.
* * *
V. M. Baler, V. M. Katkov, and V. S. Fadin.
Radiation of Relativistic Electrons. Atomizdat,?
Moscow, 1972
This book is devoted to a systematic presentation of the theory of bremsstrahlung and pair production
in the passage of a high-energy particle through an externally applied field, or in the collision of high-
energy charged particles, with acknowledgement of polarization effects and spin effects. Special features
of electromagnetic processes at high energies which aid in simplifying the radiation of relativistic electrons
appreciably are given close attention. The book is the first monograph to appear with a detailed discussion
of this realm of electromagnetic phenomena.
The book is intended for specialists in the field of high-energy physics and elementary particles, who
are concerned with the design and applications of accelerators and storage rings, and may also be found
useful by instructors and graduate students in physics.
* * *
E. Kowalski. Nuclear Electronics (translated
from the English), Edited by I. V. Shtranikh.
Atomizdat, Moscow, 1972
Applications of the widely used nuclear radiation detectors, the particular features of the pulses they
generate, pulse shaping, amplification, discrimination of signals from similar detectors, performance
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of various arithmetic operations with those signals in analog form, and so on, as well as details of pro-
cessing those signals, in relation to the statistical nature of their pulse height and time distribution, are
discussed. Devices converting the pulse height of signals to analog form, devices recording time intervals,
digital pulse counters and digital logic devices for performing arithmetical operations on them on the basis
of applications of Boolean algebra, are described.
The design principles of recording single-channel and multichannel systems, including the method
of direct application of digital computers for that purpose, are outlined in brief.
The book is written for experimental physicists; it will also be useful to engineers working in elec-
tronics, and to instructors and students at engineering colleges.
* * *
A. Lichtenberg. Particle Dynamics in Phase Space
(translated from the English). Atomizdat, Moscow, 1972
This book deals with the fundamentals of the theory behind the concept of phase volume, and the
problems concerned with utilizing the concept in calculations of beam optics, acceleration and confinement
of charged particles. A unified presentation of these topics is made available for the first time.
The author develops the concept of phase space in the theory of the motion of charged particles in
electromagnetic fields. Some basic concepts of phase space are introduced, and the discussion proceeds to
the adiabatic invariance of systems with one or more degrees of freedom, while the theory of transforma-
tion of phase space is presented. Topics in the theory of oscillations, optics of beams of charged parti-
cles, particle dynamics in accelerators, and confinement and heating of plasma, are discussed from the
vantage points of the general theory. In particular, a detailed treatment is given of such topics as the
effect of radiation and space charge on the motion of particles, maximization of particle capture ef-
fectiveness in a synchrotron, multiturn injection into storage rings, plasma heating techniques, and parti-
cle capture in magnetic traps.
The monograph is written for a broad range of research scientists, graduate students, and senior
undergraduates specializing in the areas covered.
* * *
B. Taylor, V. Parker, and D. Langenberg.
Fundamental Constants and Quantum
Electrodynamics (translated from the
English). Atomizdat, Moscow, 1972
This book constitutes a unique survey of precision measurements of the fundamental physical con-
stants, and contains recommendations on their use in several branches of physics, ranging from solid
state physics to quantum electrodynamics.
There is a detailed survey of experimental papers on measurements on the fundamental physical
constants and their most highly refined values.
The book is written for a broad readership of experimental physicists, and can be used by specialists
working in different branches of physics.
* * *
J. Hirt and I. Lote, Theory of Dislocations (translated
from the English), Yu. A. Osip' yan and
E. M. Nadgornyi (Editors). Atomizdat, Moscow, 1972
This book can be regarded as the first textbook, in the world literature, on the theory of dislocation.
The presentation is given on a fairly high and up-to-date scientific level, reflecting achievements scored
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in recent years in the field of dislocation theory. The properties, behavior, and interaction of dislocations
in crystalline materials is discussed in detailed fashion, with a rather serious mathematical groundwork
built up for the physical models considered. The effect of the crystal structure on the properties and be-
havior of dislocations is demonstrated. -Reference material at the back of the book covers elastic constants
of materials and values of surface energies.
The book is written for research scientists engaged in various branches of the physics and chemistry
of solids, and in metal physics. The text is of especial value for its independent development to specific
applied problems which will be of interest to a broad range of specialists.
12
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ARTICLES
DOSIMETRY OF y AND NEUTRON RADIATION WITH
A SCINTILLATION SPECTROMETER
V. P. Kovalev, S. P. Kapchigashev, UDC 539.12.08
and L. P. Pavlov
This paper discusses the possibility of using a scintillation spectrometer having a stilbene crystal
as a dosimeter for the dosimetry of mixed y and neutron radiation. The use of the well-known principle of
pulse-shape discrimination makes it possible to determine the dose from neutrons and y rays separately
by means of such a technique.
'y-Ray Dosimetry
If (dN/dEe)(Ee) is the differential spectrum of the electrons produced in the scintillator, the dose
deposited in tissue by y rays from an arbitrary spectrum can be computed from the expression
D = AQ (Ey) K [D; + (1)
where A is a calibration coefficient; K is a coefficient for conversion from absorbed energy to dose, rad;
Eemax.
Q(Ey) is a conversion coefficient from dose measured in the scintillator to dose in tissue; Dte = (dN
Eeth Ee th
/dEe) (Ee)Eede; D: = (dN/dEe) (Ee) EedEe. The quantity D; defines the dose from electrons with en-
ergies below the threshold for separation of the neutron and -y-ray components and is not measured directly.
The fraction in this dose depends both on the 'y-ray spectrum and on the value of the threshold (Eeth). In
general, this quantity also determines the inaccuracy of 'y-ray dose measurements in mixed fields.
However, experimental studies have shown that near the threshold for separation of the ('y ?n)com-
ponents, the instrumental spectrum of electrons" in a stilbene crystal can be described with satisfactory
accuracy by the function (dN/dEe)(Ee) = Ce-aEe. The studies were carried out over the -y-ray energy range
0.2-4.5 MeV. In this case, only the quantity a in the exponent varies.
Thus the contribution D" to the total dose can be determined by extrapolation of the dependence (dN
/dEe) (Ee) from the region of electron energies above the threshold to the unmeasured energy region (Ee
< Eeth). A similar method for estimating D: was used in [1] in studies of the 'y-ray dose from various
targets bombarded by a particles with an initial energy of 42 MeV. Calculations showed that the conversion
coefficient Q(E), which takes into account the lack of tissue equivalence for a stilbene crystal in the 'y-ray
energy range from 0.1 to 20 MeV, differed from 1 by no more than 1-3%.
TABLE 1. Dose Ratios for Neutrons and
'y-Rays
Source
This work
Reference
[7] I [6] I [5] [6]
Pu?Be
Po?Be
1,7+0,2
0,07
2,5
2,5
1,84
2,5
TABLE 2. Doses and Dose Ratios of Neutron
and y Components of Radiation Field
Layer thick-radD
ness, cm
rad
DnIDv
n' /
h- A
I
D
Y ' h-?A
0
11,4
3800
3.10-3
50
0,38+0,04
0,18+0,01
2,1+0,2
Translated from Atomnaya Energiya, Vol. 34, No. 1, pp. 7-10, January, 1973. Original article
submitted June 7, 1971.
0 1973 Consultants Bureau, a division of Plenum Publishing Corporation, 227 West 17th Street, New York,
N. Y. 10011. All rights reserved. This article cannot be reproduced for any purpose whatsoever without
permission of the publisher. A copy of this article is available from the publisher for $15.00.
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Dose in stilbene
2,2
1,8
1,4
7
5
5
4
3
2
0
(211
1111
1111111_
'??
....... ?? ? ? ? ???????????? ?????????????????????????????"'
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Dose in tissue
????
??????..
.??????????S
??????
.....
........ ............
???? .c?e..????
.??.- 56P...?'
? .?'" ????
...?????
....".
???????
...*** ?
????
..???
0,3 0,4' 0,5
2 3 4 56 7 8 9 10 12
Fig. 1. Dependence of deposited dose on fast-neutron energy for
tissue and stilbene.
Neutron Dosimetry
In interactions with organic scintillators, the energy of fast neutrons is transformed into the energy
of charged particles mainly through (n?p) scattering by hydrogen and also because of elastic scattering and
(n, a) reactions in carbon. However, a carbon nucleus acquires an insignificant amount of energy through
elastic scattering and the efficiency for conversion of this energy into light is considerably less than that for
recoil protons. The cross section for the C12 (n, a)I39 reaction is several order of magnitude less than the
scattering cross section for hydrogen.
Thus only (n?p) scattering in hydrogen makes a contribution to the measured dose in neutron dosi-
metry with a stilbene crystal.
If (dN/dE )(E ) is the differential spectrum of recoil protons, the dose deposited in tissue by neutrons
P p
from an arbitrary spectrum can be calculated (as above) from the expression
D = AQ (E) K [D;,+ Dc,]. (2)
In the general case, the conversion coefficient Q(En) depends on the neutron energy and is determined
in the following manner:
Q(En) ?
EH (E.)
(3)
where h is the weight percent content of the i-th element in tissue; Ki(En) is the energy transferred to the
i-th element (kerma) by neutrons with an energy En as the result of all possible nuclear reactions; flland
Kii (En) are respectively the percent content of hydrogen in stilbene and the energy transferred to a hydrogen
nucleus by neutrons with an energy En.
Calculations of the coefficient Q(En) were made for the neutron energy range 0.2-14 MeV on the basis
of kerma data for hydrogen, carbon, nitrogen, and oxygen given in [21.
The chemical composition of tissue was assumed to be the following (in wt.%):H, 10; C, 12; N, 4; 0,
73; and other elements, 1. The chemical formula for a stilbene crystal is C14H12 with the following
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dN
d Ee e
41000
3000
2000
1000
???????????
I
I I I I I 1 1 1 1 1 1 1 1 1 1 1 1 1
?
0,2 0,4 0,6 0,8 1,0 1,2 44/ 1,6 1,8 2,0 2,2 2,41 2,6 2,8 3,0 42 3,6 3,8 450 4.2 4/4
E, MeV
Fig. 2. Dependence of intensity (dN/dEe)Ee on electron energy.
composition: H, 6.7 wt.%; C, 93.3 wt.%. Results of a calculation of the coefficient Q(En) as a function of
neutron energy are shown in Fig. 1. The peaks in the region of 0.44 and 1 MeV are the result of resonances
in the (n, y) reaction in oxygen. The slow rise at neutron energies above 20 MeV is explained by the
decrease in the (n?p) scattering cross section in hydrogen and the simultaneous increase in the cross sec-
tions for neutron interactions in carbon, nitrogen, and chiefly oxygen. Despite some fluctuations, the
function varies from 1.6 to 1.8 in the energy range up to 10 MeV. The average value of the conversion
coefficient for this range is given as Q(En) = 1.7 ? 0.1, which can lead to an uncertainty of the order of 6%
in the conversion from measured to true tissue dose.
Where the light output of a stilbene crystal for electrons above a few tens of keV is independent of
electron energy and consequently the measured pulse height distribution is the electron spectrum, for
protons the light output depends significantly on energy and the spectrum of recoil protons is determined
from the instrumental distribution dN/ds in the following manner:
dN
d E p
10000
9000
8000 - ????%:?????????
7000 - ????
6000 - ??
??...
5000 - ...
???
4,..
dN dN ds
dE (1'1') = cis dE ?"Pl.
4000 -
3000
2000
1000
900
800
700
500
)1
???
?????
? .?:.?
????..
???
??
1 2 3 7 8
Ep , MeV
Fig. 3. Dependence of intensity (dig/dEp)Ep on recoil pro-
ton energy.
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dV
? /V(V)
dE
800
500
400
300
200
100
10
? ?
? ?
_
?
?
?
*es
?
?
el'e?
?
? tos
? ?
? ?
?
?
?
0 1 2 3 4 5 6 7 8 .9 10
E. MeV
Fig. 4. Spectra of secondary electrons and recoil pro-
tons produced by mixed radiation.
In this work, data on the light yields ds/dEp given in [3] was used in the determination of recoil proton
spectra. It should be noted that the measurement accuracy for a neutron dose is somewhat poorer than the
accuracy of a y-ray dose measurement and is mainly determined by the discrimination level for y-ray
pulses.
Dose Characteristics of (Pu?Be) Source
To illustrate the possibilities of the dosimetry method presented above, studies were made of the
ratio of the dose from neutrons and y-rays from a Pu? Be source. Measurements were made with a neu-
tron spectrometer having a stilbene crystal 30 x 30 mm in size and an FEU-13 photomultiplier. The
spectrometric threshold for electrons was 0.1 MeV with a suppression coefficient of ?103 for neutron or
y. radiation.
Figures 2 and 3 show curves for the energy dependence of the intensity (dN/dE)E for electrons and
recoil protons in the case of a Pu?Be source having a strength of 4.6 ? 105 n/sec. The ratio of neutron dose
to 'y-ray dose obtained from this data is shown in Table 1. The table also shows calculated results for the
dose ratio based on the study of y-ray yield per neutron for a Pu?Be source [4] and on data from [5,6].
Satisfactory agreement of the dose ratio Dn/Dy obtained in the present work with calculated results
is observed. At the same time, a considerable disparity is observed between the results obtained for the
quantity Dn/Dy and the data given in [71.
Study of Mixed-Radiation Source (LUE-2 5)
A study was made with an LUE-25 linear electron accelerator. A layer of iron 50 cm thick was used
as a shield which was located at an angle of 120? to the direction of the electron beam. The distance from
the tungsten target (a disk 40 mm in diameter and 8 mm thick) to the front wall of the shield was 700 cm.
The scintillation dosimeter was located directly behind the shield. The spectra of secondary electrons and
recoil protons produced in the stilbene crystal are shown in Fig. 4. The neutron dose (Dn) and y-ray dose
(Dr) behind the layer of iron obtained from this data were reduced to the dose values at a distance R = 50
cm and are given in Table 2. The table also gives the value of the mixed-radiation dose in the absence of
a shield (x = 0). In this case, the y-raydose was measured with a ferrous sulfate dosimeter, and the
neutron component of the total dose was determined by calculation based on the known integral yield of
16
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Declassified and Approved For Release 2013/09/15: CIA-RDP10-02196R000400010001-9
neutrons. The results of the study show that the use of an iron shield 50 cm thick leads to an increase in
the Da/Dy ratio by approximately a factor of 103 in the mixed-radiation field from the target of a linear
electron accelerator.
The authors are grateful to N. V. Rodionov for help in the construction of the neutron scintillation
spectrometer.
LITERATURE CITED
1. S. S. Omarov et al., At. Energ., 26, 390 (1969).
2. R. Bach and R. Caswell, Rad.. Res., 35, 1 (1968).
3. Yu. A. Kazanskii et al., At. Energ., 20, 143 (1966).
4. D. Drake et al., Nucl. Instrum. and Methods, 62, 349 (1968).
5. N. A. Bak and N. S. Shimanskaya, Neutron Sources [in Russian], Atomizdat, Moscow (1969).
6. A. T. Bakov et al., Neutron Monitoring, IAEA, Vienna (1967), p. 201.
7. G. M. Fradkin, Isotopic Neutron Sources [in Russian], Gosatomizdat, Moscow (1963).
Declassified and Approved For Release 2013/09/15: CIA-RDP10-02196R000400010001-9
17
Declassified and Approved For Release 2013/09/15: CIA-RDP10-02196R000400010001-9
CHARACTERISTICS OF THE PERSONNEL NEUTRON
TRACK DOSIMETER DINA
I. B. Keirim-Markus, T. V. Koroleva, UDC 539.12.08
S. N. Kraitor, and L. N. Uspenskii
The personnel neutron dosimeter DNA based on the use of fission fragment track detectors containing
Np237 behind a B10 filter and U235 was proposed in [1]. The composition of the fissile isotopes in the dosi-
meter and the filter thickness were chosen so that its energy characteristic best reproduced the energy
dependence of neutron kerma or of neutron kerma equivalent, i.e. , those dosimetric quantities which should
be measured by a personnel dosimeter. In accordance with this, the measurement of neutron dose is re-
duced to the counting of tracks from fission fragments and the multiplication of the resultant number of
tracks by the track value. The latter is weakly dependent on the neutron spectra which may be encountered
during irradiation. Estimates made in [1] showed that the spread in track value does not exceed 15% for
actual neutron spectra in rooms.
A study was made of the characteristics of the DNA personnel dosimeter which are important in its
practical use (dosimeter sensitivity, dependence of its readings on distance from surface of the body and
angle of irradiation, effect of neutron spectrum on track value).
Experiments were carried out with a dosimeter consisting of two fission fragment detectors, in one
of which there was a Np237 target with a boron filter and in the other, a U235 target (Fig. 1). Fission
23 55
;919 .6.X.V...:eccf6S1?262;f4..:4
tfAir.ESOINPM1110
..11: I =NW ?".1?16.1., ?
'
Fig. 1
E E
a)
330 2 30 ;74
a)
4 220 20
110 10
0 0,25 0,5 0,75 1,0
B10 thickness, g/cm2
Fig. 2
Fig. 1. Construction of neutron personnel dosimeter. a) De-
tector containing U235; b) detector containing Np237; 1) case; 2)
spring; 3) polyethylene cap; 4) B10 filter 0.1 g/cm2 thick; 5)
target; 6) glass track detector.
Fig. 2. Track value of the personnel dosimeter for accident
(1) and routine (2) monitoring and maximum measurement error
(3) as functions of boron filter thickness.
Translated from Atomnaya Pnergiya, Vol. 34, No. 1, pp. 11-15, January, 1973. Original article
submitted February 23, 1972; revision submitted May 29, 1972.
18
? 1973 Consultants Bureau, a division of Plenum Publishing Corporation, 227 West 17th Street, New York,
N. Y. 10011. All rights reserved. This article cannot be reproduced for any purpose whatsoever without
permission of the publisher. A copy of this article is available from the publisher for $15.00.
Declassified and Approved For Release 2013/09/15: CIA-RDP10-02196R000400010001-9
Declassified and Approved For Release 2013/09/15: CIA-RDP10-02196R000400010001-9
2 4 6
Distance, cm
Fig. 3
8
10
2 4 6
Neutron energy, MeV
Fig. 4
8
10
Fig. 3. Personnel dosimeter readings as a function of distance to phantom surface. a)
Detector containing Np237 + 0.1 g/cm2 Bil3; b) detector containing U235; dashed lines)
measurements without phantom; 1) total reading of detector with U235; 2) thermal neu-
trons from phantom; 3) calculation for disk isotropic source.
Fig. 4. Energy dependence of track value for personnel dosimeter (1), and detector
containing U238 (2) for irradiation at angles of 0 (dashed line), 45 (straight line), and 90?
(dash-dotline).
fragments were recorded by track detectors made of silicate glass which were etched after irradiation for
9 min in 5% hydrofluoric acid and counted under an MBI-9 microscope. Target and detector areas were
1 cm2 and target thickness was 0.2-0.5 mg/cm2. Fast-neutron calibration was done with a Pu?Be source
and thermal calibration with a Pu?Be source in a paraffin moderator.
The personnel dosimeter track value A(E) is given by the expression
6(E)
A (E) = f (E) gin ,
(1)
where b(E) is the specific kerma or kerma equivalent for neutrons of energy E; o-f(E) is the fission cross
section; Ef is the fission fragment detection efficiency; n is the number of nuclei of the fissile isotope in the
dosimeter. The track value averaged over a neutron spectrum for optimal isotopic composition in the
dosimeter (99.76% Np237 and 0.24% U235) was calculated from
6 (E) (1)(E) dE
?(2)
( of eff NP &pup (E) dE
where (Jefff Np (E) is the effective fission cross section for Np237 behind a boron filter, and co (E) is the dif-
ferential neutron fluence.
Since sensitivity depends on filter thickness, calculations were made for various Bt? thicknesses.
Computed results averaged over the set of spectra [1] for kerma and kerma equivalent are shown in Fig. 2.
The same figures gives the dependence of the maximum error of measurement obtained in [1] for a set of
actual neutron spectra. Sine the optimal composition of isotopes in the dosimeter is identical for the
measurement of kerma and kerma equivalent, the errors are the same. Thus the DINA dosimeter can be
used for accident and routine monitoring merely by changing the dose value of a track.
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Declassified and Approved For Release 2013/09/15: CIA-RDP10-02196R000400010001-9
TABLE 1. Track Value for Np237 in the DINA Neutron Personnel Dosimeter and for a
U238 Detector at Various Irradiation Angles
Detector
Track value, mrad/track? mg
Pu -Be source
fission spectrum reactor spectrum
o? 90?
0? I 45? I 90? 00
45?
900
TYINA personnel dosi-
meter
238
2,20
8,7
2,35
10,0
2,45
10,9
2,10
10,0
2,21
11,4
2,30
13,3
2,41
14,1
2,52
16,4
2,62
19,1
Figure 2 indicates that the optimal thickness of the Bi? filter is 0.1-0.15 g/cm2. For this thickness,
track value for accident monitoring is about 2 mrad/track ? mg Np237, and for routine monitoring, about 20
mrem/track ? mg Np237. Such a value makes it possible to measure neutron dose in the 5-5000 rad range
(this corresponds to the recommendations of the IAEA [2])with a statistical error no worse than 2% and to
measure a dose equivalent of 0.5 rem and above (which corresponds to the maximum permissible quarterly
dose in accordance with the requirements of NRB-69 [3]) with a statistical accuracy no worse than 15%.
Since a personnel dosimeter is intended for the measurement of the maximum value of neutron dose
at the surface of the body, it is important to evaluate the effect of possible poor approximation of the
dosimeter to the body. These evaluations were made by an analysis of the dependence of DINA dosimeter
readings on distance to the surface of a tissue-equivalent phantom of the human torso. The measurements
were made in a collimated beam from the IBR reactor at JINR [4] at 10 m from the core. The phantom was
an elliptical cylinder having semiaxes of 12.7 and 18 cm and a height of 60 cm, which was filled with a
tissue-equivalent liquid; the thickness of the vinyl plastic shell of the phantom was 0.3 cm [5]. Dosimeters
were set up on the line of the minor semiaxis at various distances from the surface of the phantom with
mutual shielding being avoided. The irradiation field was uniform within the limits of a circle 40 cm in
diameter.
Figure 3 shows measurement results for detectors containing Np237 and U235. Readings of the detector
with Np237 at the phantom surface were a few percent higher than in air because of fast neutron albedo;
furthermore, they depended weakly on distance to the surface since the fast neutrons from the reactor are
the predominant factor.
Readings from the detector containing U235 depend significantly on distance since the thermal neutron
fluence from the phantom is dominant and, at the phantom surface, it is seven times greater than the con-
tribution of thermal neutrons incident on the detector directly from the core. As the distance from the
surface increases, the thermal neutron fluence decreases. This dependence is close to that calculated for
a disc isotropic source 40 cm in diameter (see Fig. 3). It was obtained on the basis of [6] from
"Dtherm (z) =-1n (i+-) , (3)
where A is a constant, z is the distance from the phantom surface, and R = 20 cm is the radius of a disk
source equal to the radius of the neutron beam. The calculated dependence was normalized to the experi-
mental values at a distance of 2.5 cm from the phantom.
Measurements were made with an Np237 detector for phantom irradiation at angles of 45 and 90? to
the surface. These results were similar to those for irradiation along the normal within the limits of
experimental error ('10%).
Thus the readings of the personnel dosimeter for intermediate and fast neutrons within the range of
10 cm from the surface of the body are practically unchanged with distance. Therefore, there is no need
to place the dosimeter close to the body (without loss of accuracy, it can be fastened to a pocket on pro-
tective clothing and not on a belt). The kerma of thermal and slow neutrons vary by approximately a factor
of two at these distances; however, the thermal neutron contribution to total neutron kerma is small as a
rule.
When using an accident personnel dosimeter, it is important that its readings do not depend on the
direction of irradiation. In track detectors, however, such a dependence appears with fast neutron fission
because of the anisotropy of the fission fragment distribution [7]. To evaluate this factor, the track value
for Np237 in the DINA personnel dosimeter was calculated for various angles of irradiation. The calculation
made use of the expression
20
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Declassified and Approved For Release 2013/09/15: CIA-RDP10-02196R000400010001-9
TABLE 2. Characteristics of the DINA Personnel Neutron Dosimeter
Neutron spectrum
Dosimeter location
' Track value
Kerma measurement, rad m rad
Maximum error
. sweittliorttrreschtoti3d
detectors, %
DINA do-1I
simeter
set of
threshold
detector
Ionization
chambers
track ? mg
N p237
experi-
ment
calcu-
lation
Air 47,5
45,0
-
2,13
5,2
6,0
IBR spectrum at INA outside
water filter (4 cm thick)
Front surface of phantom 49,5
Rear surface 1,47
48,3
1,46
-
-
2,15
2,36
4,5
0,5
4,1
-1,5
Air 9,0
8,5
-
2,13
5,4
6,6
Fission neutrons outside
water shield
Front surface of phantom 9,6
9,2
9,7
2,18
4,4
5,3
Rear surface 1,41
1,46
-
2,30
-3,5
-2,0
Fission neutrons outside
iron shield
Front surface of phantom 1,94
2,08
2,0
2,48
-6,7
-2,3
Fission neutrons outside
iron-polyethylene shield
Front surface of phantom 2,37
2,65
2,58
2,50
-10
-6,6
IRT-1090, boron-lead
filter
Air 28,2
26,6
26,1
2,12
6,0
7,0
6(E)
A (E, 0)
= c r (E) Cf (E, 0) n
(4)
where 0 is the angle of irradiation with respect to the normal to the detector surface, and ?f (E, 0) is the
detection efficiency, taken from [8], for fission fragment detection by a silicate glass track detector.
Computed results are shown in Fig. 4 for irradiation angles of 0, 45, and 90?. Shown there also for
comparison are the results of similar calculations for a detector containing U238, which is also used in
personnel dosimeters in certain cases [9]. As should be expected, the track dose value depends on angle
of irradiation. Its variation for irradiation at angles of 0 and 90? is 5-10% for Np237 and 15-25% for U238.
In dosimetric measurements, one must deal not with monoenergetic neutrons but with some spectrum
cp(E); therefore a track value averaged over several spectra was calculated. We chose the spectrum from
a Pu-Be source, which is often used in dosimeter calibration, the fission spectrum, and the spectrum from
a water-cooled, water-moderated reactor [10], which is close to that met in practice. Averaging was
performed in accordance with
(E , 0) (E)dE
(E)dE
(5)
The results are given in Table 1. It is clear that the greatest variation in averaged track value is observed
for U238, in which fission anisotropy is greater than in Np237. Such a variation along with the uncertainty in
irradiation direction leads to additional error in the evaluation of neutron dose. It is small, amounting to
3-5%, for a Np237 dosimeter, but is considerably higher (15-22%) for U238 and significantly limits the ac-
curacy of dosimetric measurements.
The angular dependence of the readings from the DINA personnel neutron dosimeter and from a de-
tector containing U238 were determined experimentally at the IBR reactor at JINR by irradiation of the
dosimeters with a collimated beam of neutrons at angles of 0, 45, and 90? to the target surface. With
respect to the 45? angle, the variation of track value for U238 was 18% (0? angle); the corresponding values
for Np237 were 3% and -2.7%. These quantities correspond to the values calculated from Eq. (5) for the
neutron spectrum from the IBR reactor at JINR measured in [11].
The data presented above was obtained for dosimeters in air and give an upper estimate of the angular
dependence. At the surface of a phantom, the effect of anisotropy on the value of the dose will be some-
what less because of the increase in the contribution to the dose from intermediate neutrons having an
21
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Declassified and Approved For Release 2013/09/15: CIA-RDP10-02196R000400010001-9
isotropic angular distribution. For U235, the fission of which is produced almost entirely by thermal neu-
trons, angular dependence is absent both in air and at the surface of a phantom because the distribution
of thermal neutron fission fragments is isotropic.
To determine the effect of the response to hardness on the readings of the DNA personnel neutron
dosimeter, it was irradiated by fission neutrons outside shields of water, iron, and iron?polyethylene. At
the IBR reactor at JINR, dosimeter irradiation was outside a layer of water 4 cm thick and at the IRT-1000
reactor, outside a boron?lead filter [12] with the dosimeters being located both in air and on the surface
of a phantom. The results are given in Table 2; shown there also are values of neutron kerma obtained at
the same points with a spectrometric set of threshold detectors [11, 13] and kerma values obtained by V. I.
Tsvetkov and E. N. Chernov with tissue-equivalent and graphite ionization chambers [14]. Table 2 indi-
cates that the results of kerma measurements by the various methods agree with the limits +10%. In
evaluating the response to hardness, the maximum error ri of the kerma measurements was calculated
with respect to the spectrum obtained from the set of threshold detectors. It agrees with the error in
measurement of kerma equivalent and is given by
11-1
(E) (E) dE
(6)
?
(E) (E) dE
The errors shown in Table 2 are in agreement with experimental errors. The same table gives track
values of the DINA personnel dosimeter for various neutron spectra. Its average value, 2.3 mrad/track
? mg Np237, has a variance of ?8% and agrees with the calculated value of 2.2 mrad/track ? mg Np23 7 (see
Fig. 2)
The authors thank L. B. Pikeliner, N. N. Khotyko, V. I. Tsvetkov, and E. N. Chernov for valuable
discussions and for help with the measurements.
LITERATURE CITED
1. I. A. Bochvar et al., Handling of Radiation Accidents, Proc. Symp, IAEA, Vienna (1969), P. 235.
2. Nuclear Accident Dosimetry Systems, Proc. IAEA Panel, Vienna (1970).
3. Radiation Safety Standards (NRB-69), Atomizdat, Moscow (1970).
4. G. E. Blokhin et al., At. Energ. , 10, 437 (1961).
5. V. G. Zolotukhin et al., Neutron Tissue Doses [in Russian], Atomizdat, Moscow (1972).
6. B. Price, C. Horton, and K. Spinney, Radiation Shielding [Russian translation], Izd-vo Inostr. Lit.,
Moscow (1959).
7. T. V. Koroleva and S. N. Kraitor, At. Energ. , 31, 52 (1971).
8. T. V. Koroleva and S. N. Kraitor, in; Metrology of Neutron Radiation at Reactors and Accelerators,
VNIIFTRI, Moscow (1971), p. 74.
9. G. M. Obaturov and Yu. K. Chumbarov, in; Problems of Dosimetry and Radiation Shielding [in
Russian], No. 10, Atomizdat, Moscow (1969), p. 155.
10. Yu. A. Egorov, V. I. Zharkov, and V. V. Postnikov, At. Energ. , 28, 170 (1970).
11. K. K. Koshaeva, S. N. Kraitor, and L. B. Pikel'ner, At. Energ. , 32, 68 (1972).
12. Yu. I. Bregadze et al., At. Energ. , 12, 537 (1962).
13. T. V. Koroleva, K. K. Koshaeva, and S. N. Kraitor, At. Energ. , 32, 157 (1972).
14. V. N. Khrapachevskii, in; Biological Effects of Fast Neutrons [in Russian], No. 1, Naukova Dumka,
Kiev (1969), P. 11.
22
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Declassified and Approved For Release 2013/09/15: CIA-RDP10-02196R000400010001-9
ACTIVATION OF THE WATER COOLING
SYNCHROCYCLOTRON COMPONENTS
M. M. Komochkov and Yu. G. Teterev
UDC 539.16.04: 621.348. 67
Recent improvements to the 680 MeV proton synchrocyclotron in the Laboratory of Nuclear Problems
of the Joint Institute for Nuclear Research, aimed at increasing the intensity of the proton and secondary-
particle beam by several tens of times, have necessitated a more precise study of the degree of radiation
hazard due to the activation of the water cooling various parts of the accelerator. It is important to know
tha laws governing the accumulation of radioactivity in the water and the changes taking place in this radio-
activity. In order to obtain this information we studied the amount of y-radioactive isotopes with a life of
more than 20 min in the water cooling those synchrocyclotron components subjected to the most intensive
irradiation, and also measured the field of y-radiation close to the tubes of the cooling system. Similar
investigations were carried out on a linear electron accelerator by Warren [1].
Cooling System
The cooling system of the synchrocyclotron constitutes a closed circuit communicating with the
atmosphere. The volume of the circuit is ?36 m3. The accelerator and the water-supply system of the
cooling circuit are sited in different buildings. The heated water from the accelerator building passes into
the building containing the heat exchanger and recirculation pump through six tubes 130 mm in diameter,
which at the same time act as a reserve volume.
io5
10
S. 10
Direction of motion of the water
-t-
fft
fttf+
t
10 ? . ........
0 100 200 300 400
2
++++
ff++Ifififtf+4
300 200 700 0
Distance from the entrance to the tunnel from the first vessel of the synchro-
cyclotron, m
Fig. 1. Distribution of dose rate along the tubes of the cooling
circuit: A) close to the tube; 0) at a distance of 90 cm from the
first tube; 1) with the accelerator working; 2) after stopping the
accelerator (after 3.5h).
Translated from Atomnaya Energiya, Vol. 34, No. 1, pp. 17-22, January, 1973. Original article
submitted March 21, 1972.
1973 Consultants Bureau, a division of Plenum Publishing Corporation, 227 West 17th Street, New York,
N. Y. 10011. All rights reserved. This article cannot be reproduced for any purpose whatsoever without
permission of the publisher. A copy of this article is available from the publisher for $15.00.
23
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Declassified and Approved For Release 2013/09/15: CIA-RDP10-02196R000400010001-9
8.103
2103
1
I
8?
I
i--1-1-
1-
H
--!"1-
1--F--
InIraE
NE?IIIIMMEM?WWIIIIIIIIMM
IMEINIMI
111??????????=1?????????????????11?211????
e????????????????????????????
HIM=
iimmagum???????????????????????
mormommmisimim
maa???????????????
EN
MEM
72,78
MENniliiiiiini
EMMINIENNIIMMENEWN01111111111111w
NENESEMMEMOsimmuniol
pa
? ru.
N 1
? I
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wEll
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1.11,...............,...,......,...
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mu
'rill
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v1'1111111
iiin
mom?MI w.Luiii
1.1.
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im?
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ni
1
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?r
in
?
?1.1
1
im ?milli
kill.
?
Allpiiiii
milinsia
nun ????????
imiminiiiiiial
mmHg p
?al
In 1
m 11
ME ?
I; IR
I 1 il
1
*
!pp
ppm
mom
ii mir,
,i PIM!
Pr
,,
100
180 260
340
420
500
58.0
660 740 320 900
980
1060
1140
1220
1300
Channel number
Fig. 2.
y-Spectrum of the dry residue of the water from the synchrocyclotron
cooling circuit measured with a Ge(Li) detector (the figures on thepeaks repre-
sent the energies of the 'y-quanta in keV).
TABLE 1. Isotopes Detected in the Cooling
Circuit and Their Activity (Measured and
calculated)
Sample
Activity of the circuit
water, decays/sec? liter
measured calculated
Coe?
17 (7)*
73
Co58
150 (60)
218
Co57
100(40)
133
Co56
35(14)
50
Mn56
50
? 1,0
? 1,0
LITERATURE CITED
1. D. P. Osanov and E. E. Kovalev, At. Energ. , 6, No. 6, 670 (1959).
2. N. G. Gusev et al? Radiation Protection of Extended Sources [in Russian], Gosatomizdat, Moscow
(1961).
3. 0. I. Leipunskii, B. V. Novozhilov, and V. N. Sakharov, Propagation of y-Quanta in Matter [in
Russian], Fizmatgiz, Moscow (1960).
4. 0. I. Leipunskii, y-Radiation in Atomic Explosions [in Russian], Atomizdat, Moscow (1959).
SEMICONDUCTOR a-SPECTROMETER FOR ANALYSIS
S. M. Solov'ev, A. N. Smirnov, UDC 535.853:543.52
and V. P. Eismont
Isotopic a-analysis based on the spectra of a-particles requires isolation of weak lines on the back-
ground of much more intense lines belonging to higher energies. The sensitivity of a spectrometer is
characterized by the ratio Na/NX, I. e. , by the ratio of the
number of counts in the channel corresponding to the peak
of a monoenergetic a-line to the number of counts in a
channel separated from the above line by a given energy
5456keV
?18 keV interval E. The spectrometer sensitivity can be improved
i?
5499 keV
by increasing its resolving power and by reducing the num-
ber of pulses having an amplitude reduced by loss of a-
10
particle energy. In [1] the values of Na/Nx have been found
as 2900, 6000, and 8000 for AE equal to 200, 400, and 800
102 5558 keV, respectively.
In this work we have selected silicon samples with
/0 -
parameters providing good energy resolution and low prob-
ability of pulses with reduced amplitudes. Two types of
1,0
silicon were used. One had a lifetime T = 1700 ?sec, a
I '
resistivity p = 1300 S2 ? cm, and a dislocation density Na
cc
25 2,0 1,5 1,0 0,4 0,2 0 E, MeV =104 cm-2; the second type was free of dislocations and had
a lifetime T = 300 ?sec and a' resistivity p = 500 S2? cm. The
detectors were prepared by the usual method except at the
Fig. 1. a-Particle spectrum of Pu238.
Translated from Atomnaya Energiya, Vol. 34, No. 1, p. 34, January, 1973. Original article sub-
mitted January 13, 1972.
43
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step of chemical etching when instead of protecting the back contact by a chemically inert layer of varnish
the contacts were covered by a vacuum attached cap of Teflon and silicon rubber. Better detectors of
both types with an active surface of 0.25 and 0.50 cm2 had inverse currents of about 0.12 ?A/cm2 with an
applied voltage of 100-200 V and provided a resolution of 15-18 keV.
The detectors used in the spectrometer had an area equal to 0.50 cm2. An aluminum diaphragm with
a polished inner edge was placed near the detector at a distance of 8 cm from the source. A Teflon dia-
phragm was placed between the source and detector for protection against a-particles scattered from the
chamber walls.
The spectrum of Pu238 a-particles is shown in Fig. 1. The source was prepared by vacuum sputtering
on a glass backing, the active spot having a diameter of 1 cm. The Na/NX ratios found with a detector
made of the first type of silicon were found to be 14,000, 28,000, 45,000, and 70,000 for AE = 200, 400, 800,
and above 1200 keV, respectively. The second type of silicon gave somewhat poorer figures.
As an illustration of the spectrometer performance we have taken the spectrum of Th229 and Th228
isotope mixture with their daughter products and determined the relative content of Th229 whose activity
was 2.20 ? 0.01% of the overall target activity.
LITERATURE CITED
1. W. Hofker et al., Philips Techn. Rev., 30, 13 (1969).
SPATIAL DISTRIBUTION OF IONIZATION INTENSITY
NEAR RADIOISOTOPIC NEUTRALIZERS OF
STATIC ELECTRICITY
A. S. Rozenkrantz UDC 621.317.7
For proper use of a radioisotopic static-electricity neutralizer it is necessary to calculate the electric
fields and the volt?ampere characteristics of interelectrode gaps ionized by radiation.. Among others,
such calculations require the knowledge of the spatial distribution of the number of ionization events Ni per
unit volume and time. For surfaces coveredwith a-and fl-active isotopes the spatial distribution of Ni can
be calculated by the method based on the thickness of the active layer da and ofthe protective layer dp
which can be represented in relative units;
=?p?,
Pm
(2)
where /am and /pm are the total ranges of the given particle in the active and protective layers.
For a-active sources the path xl to the end of the range of a particle produced in the active layer at
a depth xa = xa*/am is given by
x' (1 x:-F )
cos a
(3)
where /m is the full range of the particle in air; a is an angle between the particle trajectory and a normal
to the active layer surface at the point of escape; R is the distance from this point to the point where Ni
Translated from Atomnaya knergiya, Vol. 34, No. 1, p. 35, January, 1973. Original article sub-
mitted January 31, 1972.
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is determined. The factor x' is used as an argument in the Bragg function FB(x') and in its primitive
x?
Na (x') = FB(x') dx'
0
Since FB(x') = 0 when x' aiim = arc cos d* will
not leave the active layer.
where
It is shown that the intensity of ionization at any point is equal to
N ? 1 TAN a cos a
' 47c1md: j R2 dS 0,
so
x max
ANa= Fg(x')dx' = Na (x Max) (x' max):
X Max
d*
xinax= (I cosi) a lm? R;
cq- -
x rn. aX cos aP ) R
(4)
(5)
where T is the total relative surface activity of the layer (the number of disintegrations per unit surface and
time).
The results are given of calculating the spatial distribution near a plane active surface of PU239 for
a very thin (da* = 0.09, dp* = 0.01) and a very thick (da* = 0.5, d; = 0.5) layer; experimental and theoretical
results were compared for a practical active layer with d*a = 0.3 and dp* = 0.1 and were found to be in good
agreement.
The obtained results indicate that the layer thickness has a significant effect on the spatial distribu-
tion of N. The effect of external contamination of the active surface can be allowed for in the same number.
The method is extended to /3-active isotopes by taking into account their energy spectrum.
NEUTRON ACTIVATION DETERMINATION OF THE
CONTENT OF OXYGEN AND FLUORINE IN SAMPLES
OF ZIRCONIUM AND TANTALUM
V. I. Melent'ev, V. V. Ovechkin, UDC 543.53
and V. S. Rudenko
A neutron activation method for the separate determination of the content of oxygen and fluorine,
present in test samples based on zirconium and tantalum, is described. The samples were alternately
irradiated with 14 MeV neutrons and neutrons of a Pu238?Be isotope source (En 5 MeV), then the ?6 MeV
-y-radiation of the isotope N16, which is formed in the reactions 016(n, p) and F19(n, a), was recorded.
In this case a neutron generator with a yield of ?5 ? 109 neutrons ? sec-1, an isotopic source with a
yield of 1 ? 108 neutrons ? cm-1, and a scintillation 'y-spectrometer with NaI(T1) crystal with dimensions
Translated from Atomnaya knergiya, Vol. 34, No. 1, pp. 35-36, January, 1973. Original article
submitted June 12, 1972.
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150 x 150 mm with a depression were used. The results of the determination of the oxygen content are in
good agreement with the results of an independent method.
The method and apparatus described provide for a threshold of sensitivity of the determination of
fluorine of 1 mg in a system of repeated irradiation after 5 min. The calculated dependence of the threshold
of sensitivity of the determination of the oxygen content on the fluorine content in the analyzed samples was
obtained. For a sample weighing -10 g, the method permits measurement of oxygen concentrations 10-2%
by weight even in those cases when the ratio of F :0 contained in it is > 10.
EXPERIMENTAL INVESTIGATIONS OF MODULAR
OR SECTIONAL CONCRETE BIOLOGICAL SHIELDING
V. B. Dubrovskii, V. N. Ivanov, UDC 699.8
and I. N. Martem,yanov
The article goes into the shielding characteristics of modular concrete structures consisting of
blocks fabricated to different tolerances, and to be laid in place dry.
Experimental investigations were carried out in the caster-mounted tote box servicing a recess in
the IR-100 reactor, and using a shielded halogen p -counter (to detect the y-radiation), as well as aluminum
threshold indicators, indium resonance indicators, and URSa-7 scintillation detectors for neutron detection.
Modular concrete blocks were sized 100 x 200 x 400 mm, and the thickness of the shields investigated was
800, 1200, and 1600 mm.
It was found that the shape and dimensions of the planar horizontal joints which have a decisive ef-
fect on the shielding effectiveness of the modular structure depend on the precision to which the modular
blocks are fabricated, and that is limited by the band of linear tolerances. Blocks with specified linear
tolerancing of ?2 mm, ?5 mm, and ?7 mm were used in the experiments in order to ascertain the effect
of dimensional tolerances on passage of radiation through the structures investigated.
Relationships between attenuation of neutron flux density and the -y-radiation dose rate throughout the
thickness of the shielding, on the one hand, and the tolerances, on the other , were determined. The experi-
mental data indicate an exponential attenuation of neutrons and -y-radiation by small-block modular shield-
ing when the thicknesses are greater than five fast-neutron mean free path lengths (through monolithic
concrete shields).
The contribution made by neutrons belonging to different energy groups, and by y-radiation, to the
total dose on the other side of the shielding was determined experimentally for the modular small-block
structures, when high-energy neutrons show large anisotropy in their scattering behavior, transport of
such high-energy neutrons through attenuating regions of the shielding occurs with negligible energy loss.
As the probability of radiation leakage increases, as it does with decreasing tolerances on the modular
blocks in the modular construction, the contribution made by high-energy neutrons to the total dose rate
increases.
It was found that the shielding effectiveness of the modular concrete structures improves with respect
to the monolithic variant when the tolerances on the modular blocks are large within the range in question.
That is accounted for by the formation of steps in the horizontal joints of the reactor stacking that are open
all the way through (the height of the steps is proportional to the tolerances). When the steps in the joint
are increased, we observe a fall-off in the neutron flux density and in the y-radiation, because of attenua-
tion by the concrete at the site of the displacement.
Translated from Atomnaya Energiya, Vol. 34, No. 1, p. 36, January, 1973. Original article
submitted May 22, 1972.
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It was found that the fabrication technology of the concrete blocks manufactured for modular concrete
biological shielding must correspond to current standards and engineering specifications for the fabrication
and acceptance of modular concrete and reinforced-concrete structural members, with no special require-
ments imposed with respect to fabrication of blocks in special casing or scaffolding, nor any special re-
quirements on the finish of the surface.
PASSAGE OF RADIATIONS THROUGH JOINTS
IN MODULAR CONCRETE SHIELDING
V. B. Dubrovskii and V. N. Ivanov UDC 699.8
The article cites results of measurements of neutron flux and 'y-radiation dose rate on the far side
of shielding made up of sectional concrete blocks, with measurements taken at the outer surface of the
blocks. The dependence of the far-side radiation field on the length of the joint, at constant height and
width, and also on the height of the step in a plane joint, formed in vertical shear displacement of adjacent
blocks, was investigated. The results obtained are compared to measurements taken under similar condi-
tions on monolithic shielding made of the same concrete.
Eleven distinct compositions of monolithic and sectional modular shielding made from ordinary
concrete (p = 2.3 ton/m3) were investigated. The source of neutrons and y-radiation was the core of an
IR-100 reactor. The experimental assemblies were installed in a recess of the reactor adjacent to the
outer course of blocks forming a graphite reflector. The dimensions of the recess were such that mea-
surements could be taken on concrete structures of thickness 80, 100, 120, and 160 cm. Radiations were
recorded by a threshold indicator on the basis of the reaction A127(n, p)Mg27, by a In115(n, y)In116 resonance
indicator, by scintillation detectors responding to fast and intermediate-spectrum neutrons, by the URSa-7
general-purpose thermal neutron radiometer, and by a shielded SBM-10 halogen p -counter employed to
detect y-radiation.
Experimental findings are presented for attenuation of radiations on the far side of a plane "dry"
joint. The amount of buildup on the far side of the joint is estimated by the number of times the radiation
field was increased, as characterizing the increase in the flux or exposure dose rate beyond the joint, in
comparison to the situation on the shielded side of a monolithic integral concrete shield. It is demonstrated
experimentally that attenuation of thermal flux, epithermal flux, and of the y-radiation dose rate in "dry"
plane joints takes place at a more intense rate than attenuation of fast flux. Increases in the radiation
field are entered in Table 1.
TABLE 1. Enhancement of Radiation
Field (in relative units)
Shielding thick] Modes of radiations recorded*
ness, cm
45fI ''th
1)1,
80
3,32
2,74
3,28
100
5,18
4,80
3,44
120
13,85
5,08
5,96
160
79,40
22,40
19,30
*Gpf and cDth are respective flux densities of fast and
thermal neutrons; Dy is dose rate of y -radiation.
The effect of the size of the step T in the plane "dry"
joint on transmission of radiations was studied. The intro-
duction of this step exerted a pronounced effect on trans-
mission of high-energy neutrons, as compared to low-
energy neutrons and y-radiation. It is demonstrated that
blocks must be offset (relative to one another) in the vertical
direction not less than 30 mm when designing modular con-
crete biological shielding with spatial bonding of "dry"
concrete joints, since an increase T > 30 mm would not
bring about any substantial decrease in the field on the far
side of the shield.
Translated from Atomnaya Energiya, Vol. 34, No. 1, pp. 36-37, January, 1973. Original article
submitted June 14, 1972.
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ESTIMATION OF DIMENSIONAL-WEIGHT AND
ENERGY CHARACTERISTICS OF ELECTRON
ACCELERATORS FOR EXPERIMENTAL AND
INDUSTRIAL RADIATION INSTALLATIONS
V. S. Karmaza, I. F. Malyshev, UDC 621.384.6
and I. A. Prudnikov
The last 15-20 years have seen considerable improvement in low energy accelerators [1, 2], related
to the continuous broadening of their areas of application. At the same time, the experiments conducted
in accelerators, for a long time, fell outside the limits of laboratory investigations, but to date have
already resulted in a whole series of industrial radiation procedures [3, 4]. Beams of accelerated elec-
trons with energies from a fraction to 10 MeV are utilized and different types of accelerators are applied
in these procedures.
It is known that prior to the development of commercial or research radiation apparatus there already
arises, during preliminary design, the question of the choice of the type and basic characteristics for the
ionizing radiation source. A recommended procedure for this choice is presented in the article.
As the basic characteristics of the accelerators, there are taken: the energy of the electrons, average
strength of the beam, specific weight (ton/kW), density (ton/m3), efficiency, electron energy increase per
unit length, and overall dimensions.
The distribution of the "spheres of influence" among the most diversified types of operative acceler-
ators results from an analysis of their parameters.
Graphs, allowing one to estimate the characteristics mentioned for present-day electrostatic and
cascade generators, resonance transformers, and linear accelerators, are presented.
As an example of mobile radiation apparatus, two flaw detectors are considered on the basis of LUP-
15/1.5 and LITE-10/1 type linear accelerators.
LITERATURE CITED
1. H. Gordon and G. Behman, Particle Accelerators, Univ. Calif. Radiat. Laboratory, UCRL-9876
(1960).
2. E. Berill, Atomnaya Tekhnika za Rubezhom, No. 1, 26 (1971).
3. P. Parker, Particle Accelerators, 1, No. 4, 285 (1970).
4. Information of the All-Union Scientific-Engineering Conference on the Use of Accelerators in the
National Economy, NIIEFA im. D. V. Efremova, Leningrad (1971).
48
Translated from Atomnaya knergiya, Vol. 34, No. 1, p. 37, January, 1973.
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LETTERS TO THE EDITOR
LEAKTIGHTNESS MONITORING OF THE PRIMARY
LOOP IN STEAM GENERATORS AT NUCLEAR
POWER STATIONS USING WATER-MODERATED
WATER-COOLED POWER REACTOR
T. K. Fedchenko and A. A. Iltichman UDC 621.039.587
The process flowsheet that has been accepted, and the principles agreed upon for organizing testing
and monitoring of pressuretightness, allow us to consider the two-stage structure of the nuclear power
station as an acceptable engineering solution: information on the appearance of leaks in the primary loop
is obtained on the first level in the secondary loop, and which steam generator unit is at fault is determined
at the second level.
The arrangement of monitoring points is shown in Fig. 1, and results of calculations are entered in
Table 1.
Detection of Primary Loop Leaks in the Secondary Loop. The concentration of radioactive gases
can be measured in the main steam line upstream of the turbine (point 1), and at blowdown points from the
main ejectors of the turbines (point 2). A conventional ejector is employed in order to bleed steam up-
stream of the turbine and in order to prepare specimens for monitoring. Calculations of the effectiveness
of these monitoring techniques, based on the standard procedure, demonstrated the feasibility of carrying
out the monitoring operation at point 2, i.e. , monitoring at the principal ejector stations, which is a
technique roughly 400 times more sensitive than monitoring in the steam line upstream of the turbine.
TABLE 1. Sensitivity of Different Techniques for Monitoring Leaks in Primary Loop in Steam Gen-
erator Units
Number ofCalculated
monitoring
point
.
Variable monitored
Monitoring site
Instrument
sensitivity
leakage of primary loop
(li ters/h) at primary-loop activity.
? 10-i Ci/liter
? 10-5 Ci/liter
1
Concentration of ra-
dioactive noble gases
In steam line up-
stream of turbine
5.10-10 Ci/liter
0.32
3200
2
Concentration of ra-
dioactive noble gases
At points of blow-
down from chief
ejectors serving
turbines
540-15 Ci/liter
8. 10-4
8
3
y-radiation
Above blowdown
water pipe
0. 01 pR/sec
74
520
(1/, 8. 9 x 4. 5 mm)
4
N'6 B - radiation
In blowdown water
3 pulses/sec
1. 5
_
5
y-radiation
Above steam line
0.01 PR/sec
1600
5800
(b450 x16 mm)
6
N16 3- radiation
In steam line
3 pulses/sec
74
?
7
Activity of steam
generator blowdown
water
Downstream of ex-
pansion tank and
heat exchanger
5 10-1? Ci/liter
O. 15
1500
? Minimum leakage monitorable by this method is independent of the primary-loop fission-fragment activity.
Translated from Atomnaya Lergiya, Vol. 34, No. 1, pp. 39-40, January, 1973. Original article
submitted June 13, 1972.
0 1973 Consultants Bureau, a division of Plenum Publishing Corporation, 227 West 17th Street, New York,
N. Y. 10011. All rights reserved. This article cannot be reproduced for any purpose whatsoever without
permission of the publisher. A copy of this article is available from the publisher for $15.00.
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Fig. 1. Disposition of radiation leak monitor-
ing points: I) steam generator; II) turbine; III)
condenser; 1V) ejector; V) expansion tank;
VI) heat exchanger; VII) deaerator; VIII) pump;
a) primary-loop coolant; b) steam; c) steam
from other steam generators; d) steam to
other turbine(s); e) water from continuous
blowdown of steam generator; f) water from
continuous blowdown of other steam genera-
tors; g) water to filters of cleanup facility; h)
feedwater; i) vent to atmosphere. 1-7) Leak
monitoring points.
The method of measuring the total activity of the
primary-loop water (point 7) is a sufficiently sensitive
technique [1]. But this method shows a slower re-
sponse to changes than monitoring carried out at the
principal ejector stations (it takes anywhere from 5 to
9 min to deliver the sample from the steam generator
unit to the sensing device).
The methods of radiation monitoring at points
2 and 7 enable us to establish, quite reliably, the fact
of appearance of a leak in the secondary loop, but not
to find out which steam generator unit is responsible
for the leak.
Accordingly, measurements of the specific
activity of the secondary-loop water and of the con-
centration of radioactive gases at blowdown points from
the chief ejectors serving the turbines must be backed
up by monitoring the activity of the blowdown water
purged from the steam generators, or of the steam
directly downstream of each steam generator unit.
Detection of Damaged Steam Generator. The
activity of the secondary-loop water and of the steam
in the damaged (leaky) steam generator unit have
been calculated within 100 sec after the damage oc-
curred, e.g. , in the case of failure or rupture of a
secondary-loop pipe, and at a coolant specific activity of 10-1 Ci/liter. This time was arrived at on the
basis of the allowable time that can be allotted for pinpointing which steam generator is damaged. The
isotope composition of the fission-fragment activity in the primary loop when 1% of the fuel elements are
unsound has been calculated theoretically [2].
The mechanism by which nongaseous fission fragments disseminate through the secondary-loop piping
in response to leaks appearing in the primary loop in one of the steam generator units has been discussed
elsewhere [3]. Here we take up calculations of the specific activity of the water and steam, using a similar
procedure. The carryover coefficients for radioactive products entering the steam stream were assigned
the following values in the calculations: 1 for radioactive noble gases, 0.1 for compounds containing the
isotope N16; 2 ? 10-3 for nongaseous fission products. The assumption that radioactive gases carried out
entrained in the steam do not return to the condensate was entertained. When the specific fission-fragment
activity of the coolant is 10-5 Ci/liter, the sensitivity of the methods falls off markedly.
Induced isotopes whose concentration in the loop remains constant at any given reactor output level
were considered in the analysis. The analysis we carried out indicated that the maximum contribution to
the amount of induced activity of the coolant proper is made by the isotope N16. In calculating the N16-induced
activity, it was assumed that only 10% of the isotope formed would end up in the composition of the gaseous
compounds present, and that it would take 10 sec to transport the isotope from the point of damage in the
affected steam generator unit to the site where the sensing device was located. The y-radiation dose rate
was determined for the fission-fragment activity and for the induced activity at a distance of 10 cm from
the surface of the piping, while the y-radiation was calculated for the case where the sensing device is
accommodated in the interior of the piping [4].
As is evident from the calculations, the most sensitive method for determining which steam generator
is affected in the leakage is the method in which the p -emiss ion of the Nam isotope in the blowdown water
pipe (point 4) is measured. By taking the half-life of the nuclide (To = 7.35 sec) and the velocity at which
the water advances through the piping (0.2 m/sec) into account it is found that the 0-sensing device must
be placed in the immediate vicinity of the steam generator. The disadvantages inherent in this method,
based on measuring the y-radiation dose rate above the blowdown piping (point 3), are: 1) the inaccessibility
of the sensing deviced for servicing and maintenance while the loop is in service; 2) the need to provide
additional shielding for the device. Placement of the radiation-sensing devices in the zone accessible to
servicing lowers the sensitivity of these methods appreciably, however.
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The variant of positioning a-radiation sensors in the piping downstream of the steam generators is
interesting from this standpoint. Sampling specimens of blowdown water downstream of each of the steam
generators is a sufficiently exact method, but is not helpful in keeping up to date on recent changes inthe
system.
Consequently, it is the method of measuring the concentration of radioactive gases at points of blow-
down from the chief ejectors serving the turbines (point 2), backed up by measurements of the total activity
of the secondary-loop water (point 7), that is the most sensitive, most reliable, and most convenient in
use. In the case of a major breakdown (rupture of a pipe in the primary loop in a steam generator), it is
advised to use a 'y-radiation sensor situated above the pipe (point 5). Detection of smaller damage in a
steam generator would be best served by supplementing these methods with one of the suggested techniques
for monitoring directly at each steam generator unit.
The selection of the specific method depends on the presence of sufficiently reliable and inexpensive
sensing devices.
LITERATURE CITED
1. M. I. Arsaev et al., Proc. SNIIP, Nuclear Instrumentation [in Russian], Atomizdat, Moscow (1970).
2. L. M. Luzanova and B. G. Pologikh, Symposium on Planning Measures to Cope with Radiation
Accidents, Vienna (1969), paper Sm119/44.
3. E. Smith et al., Trans. Amer. Nucl. Soc. , 11, No. 1, 371 (1968).
4. Rockwell (editor), Nuclear Reactor Shielding [Russian translation], Izd-vo Inostr. Lit (1958).
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FUEL-ELEMENT TESTING CHANNEL LOOP
WITH NATURAL COOLANT CIRCULATION
G. A. Klochko, V. A. Kurov,
V. I. Maksimenko, A. D. Martynov,
V. G. Potolovskii, M. G. Bultkanov,
and V. M. Selivanov
UDC 621.039.54
One way to solve the problem of how to test new types of fuel-elements is to build special-purpose
stationary experimental loop devices at research reactor facilities. The design, construction, and opera-
tion of loops with complex technological equipment and fixturing, all accommodated in special separate
rooms with total biological shielding, is an expensive undertaking. One of the prominent shortcomings of
stationary loops is the impossibility of easily retooling and modifying the loop device to handle a different
type of coolant or to adjust to different conditions [1].
A design of a compact loop facility (Fig. 1) has been worked out to facilitate research on several
different types of fuel-elements at comparatively low costs.
The channel loop (Fig. 2) was designed for an official cell of the reactor in the world's first nuclear
power station [2, 31. The channel, which is designed for natural circulation of coolant, has an external
cylindrical body within which the fuel assembly, a compact shell-and-tube heat exchanger with floating
twin-chamber head, and lifting and lowering tubes for the thermocouple, are accommodated. The heat
exchanger is located at the top of the channel. The heat transfer surface is formed by a bundle of straight
tubes sized 6 x 1 mm. Coolant water flows inside the tubes in a U-shaped circuit, and the collecting and
distributing headers for the coolant are built into the head of the channel. The rotary chambers are stag-
gered in height. Baffles are placed on the shell side of the heat exchanger to bring about transverse flow
of coolant from the natural circulation loop over the tubes. The fuel assembly is accommodated within
the lifting tube (dimensions 63 x 3.5 mm).
Steel foil screens are provided in order to diminish the influx of heat from the graphite stacking of
the reactor over the length of the reactor, and in order to diminish recuperative heating of the coolant in
the lowering branch. Supply of coolant water to the heat exchanger, and withdrawal of coolant water, as
well as filling of the natural circulation loop, are achieved through ball-on-cone nipple type pipe connec-
tions.
Fig. 1. Fuel-element testing loop design: 1) channel
loop with fuel assembly; 2) thermocouples; 3) inter-
mediate loop in station; 4) flowmeter; 5) pressure
compensation device; 6) receiver tank; 7) com-
pressed-gas cylinder; 8) distillate preparation tank;
9) feedwater pump; 10) shutoff valves.
Translated from Atomnaya Lergiya, Vol. 34, No. 1, pp. 4042, January, 1973. Original article
submitted April 20, 1972.
52
O 1973 Consultants Bureau, a division of Plenum Publishing Corporation, 227 West 17th Street, New York,
N. Y. 10011. All rights reserved. This article cannot be reproduced for any purpose whatsoever without
permission of the publisher. A copy of this article is available from the publisher for $15.00.
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Fig. 2. Design of channel loop: 1)
pipe outlets for coolant water; 2)
lowering tube; 3) channel head; 4)
outer casing; 5) thermocouple; 6)
fuel assembly to be tested; 7) lift-
ing tube; 8) built-in tube-and-shell
heat exchanger; 9) floating heads of
heat exchanger.
The water pressure in the natural circulation loop is main-
tained by a gas pressure compensation device. Coolant water
makeup is handled by one of the feedwater pumps in the reactor
experimental loops. The water temperature at the channel exit
and entrance is monitored by four Chromel?Copel thermocouples
in Kh18N1OT steel capillary sized 0.8 x 0.15 mm. The following
parameters are measured as part of the job of monitoring channel
operating conditions: the pressure and the fill level in the pres-
surizer, the coolant temperature in the natural circulation loop
at the exit and entrance; the rate of coolant water flow through
the heat exchangers; the temperature of the coolant water at the
heat exchanger entrance and exit. All of the devices installed
to monitor the parameters of the loop channel are connected to
advance-warning and alarm annunciation systems. Deviations
from setpoints that are not likely to lead to dangerous consequences
are registered in a visual and audible signal. A drastic change
in parameters (such as a steep rise in the temperature of the
coolant water at the exit from the heat exchanger to excessive
levels, a drop in pressure in the natural circulation loop) bring
the scramming system of the reactor into action [2].
The channel capacity was computed with the heat source
distribution over the height of the reactor core, the effective
length of the fuel element being studied, and changes in the uni-
formity of the heat release pattern over the radius of the un-
perturbed reactor, all taken into account.
The experiments were conducted with a fuel assembly con-
sisting of four ribbon type fuel elements used in the reactor of the
Sever plant [4-6]. Uranium?aluminum alloy (UA13) 90% enriched
with U235, or 4.5 times the uranium enrichment in the Sever
plant, was used in the fuel assembly. The high enrichment in the
loop specimens of fuel elements was brought about with the object
of stepping up the rate of accumulation of fission products. Stain-
less steel cladding 0.3 mm thick was used.
The channel loop was operated at the rated reactor output
level for 11,142 h, and at 50% of the reactor power rating for
2937 h.
The parameters of the natural circulation and coolant water
loop are cited in Table 1.
Water conditions generally accepted for nuclear power
station performance were maintained [7] throughout the experi-
ment in the natural circulation loop: dry residues content 1 to
5 mg/liter; chlorine content 0.02 mg/liter; oxygen content 0.02
mg/liter; pH 6.5 to 7.5; water hardness 10 to 20 jig-equivalents
/liter; total activity 2.2 to 5.5 C Otter; iodine activity 2 ? 30-8 Ci/liter. Samples of water were taken
periodically, throughout the experiment, from the natural circulation loop, and their total activity and
iodine content were measured. No activity was detected in the coolant water during the experiment. Be-
cause of the low volume of coolant present in the natural circulation loop, the specific weight of the coolant
did not result in any appreciable change in the fill level in the gas pressurizer during the startup to shut-
down period, so that dumping and makeup of coolant were eliminated in that case.
The operating history of the loop channel over the course of two years and more demonstrated the
reliable performance and ease of maintenance of the facility; natural circulation could be used to remove
heat from the fuel assembly at heat fluxes in the neighborhood of 1.3 ? 10-6 W/m2; the cost feasibility and
effectiveness of using that type of experimental channels, eliminating the need to build expensive special
loops, was also demonstrated.
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TABLE 1
Natural circulation loop
Channel output level
Maximum heat flux from fuel element surface
Cladding temperature
Heating of water in assembly
Average water flowspeed through assembly
Average water flowspeed through heat
exchanger
Loop pressure
Coolant water loop
Pressure
Flowrate
Entrance water temperature
28 kW
1. 3. 106 W/m2
592? K
50? K
0. 38 m/sec
0. 35 m/sec
9. 106 N/1112
2.45. 106 N/m2
2. 5. 103 kg/h
300-350? K
At the present time, the underlying principle in the design of the channel loop is being developed in
various projects.
LITERATURE CITED
1. V. A. Tsykanov et al., At. Energ. , 29, 169 (1970).
2. L. A. Kochetov and G. N. Ushakov, in: Ten Years of Service of the World's First Nuclear Power
Station in the USSR [in Russian], Atomizdat, Moscow (1964), p. 20.
3. G. A. Klochko et al., USSR report presented at the Anglo-Soviet seminar on "Operation and use of
research and test reactors," Harwell, 1969.
4. V. A. ZhiPtsov et al., At. Energ., 26, 403 (1969).
5. N. M. Sinev et al. , III Geneva Conference on the Peaceful Uses of Atomic Energy (1964), Paper
P/310 (USSR).
6. E. I. Inyutin et al., Energ. , 26, 445 (1969).
7. G. N. Ushakov, The World's First Nuclear Power Station [in Russian], Gosenergoizdat, Moscow
?Leningrad (1959).
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Declassified and Approved For Release 2013/09/15: CIA-RDP10-02196R000400010001-9
EQUATION OF STATE OF UF6 FOR DENSITIES UP TO
0.01180 g/cm3 AND TEMPERATURES UP TO 367?K
V. V. Malyshev
UDC 533,12
We studied the equation of state of UF6 for densities up to 0.01180 g/cm3, pressures up to 750 mm Hg,
and temperatures up to 367?K, and also determined the saturated vapor density of UF6 and the heats of
sublimation at 296.3-327.6?K.
800
700
600
500
400
300
200
100
0
280
0,008592
ANL?ii.
Em lam
0,002983
0,001878
300
320
340 350
Fig. 1. Isochoric curves relating the UF6 pres-
sure to temperature (the figures give the den-
sity values in g/cm3 averaged over the isochores).
The measurements were made by means of a
constant-volume piezometer. The capacity of the
nickel ampoule, with its inner surface passivated
by fluorine was 3227 cm3 at t = 23?C, with an error
of 0.06%. The pressure of the UF6 in the piezo-
meter was measured by a compensation i method,
using a sensitive membrane separator between the
media [1]. The error in the counterpressure Was
no greater than 0.3 mm Hg, and the temperature
error 0.2?K. We used UF6 of purity no worse than
99.98%. The amount of UF6 in the piezometer was
determined by weighing, allowing for corrosion
losses not exceeding 0.1% of the charge.
We studied fourteen isochoric relationships
between the pressure p and the temperature, and
also the vapor tension curve p5(T) (Fig. 1). For
each temperature value the piezometer was held for
60-90 min (two-phase system) and 30-40 min.(gas
state) in order to establish equilibrium.
The experimental data for the saturated vapor
pressure of UF6 (in mm Hg) were approximated by
the equation:
TABLE 1. Dependence of pv and r on Tem-
perature
T., K
Pv?X 103 , g/cm3
r, kcal/mole
296,3
303,6
308,4
312,5
315,7
318,4
318,6
321,1
321,7
323,3
324,0
324,8
325,8
327,6
1,881
2,987
3,993
5,077
6,136
7,190
7,270
8,322
8,597
9,388
9,780
10,22
10,77
11,81
11,80
11,75
11,68
11,63
11,50
11,38
11,38
11,36
11,35
11,31
11,26
11,23
11,24
11,21
Translated from Atomnaya Energiya, Vol.' 34, No. 1, pp. 42-44, January, 1973. Original article
submitted February 2, 1972; revision submitted August 15, 1972.
1973 Consultants Bureau, a division of Plenum Publishing Corporation, 227 West 17th Street, New York,
N. Y. 10011. All rights reserved. This article cannot be reproduced for any purpose whatsoever without
permission of the publisher. A copy of this article is available from the publisher for $15.00.
55
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Declassified and Approved For Release 2013/09/15: CIA-RDP10-02196R000400010001-9
2808.8
lg p, =- 12.2250 0.0025309 T,
(1)
which described the experimental data with an error under 0.5%. The differences between the results and
those of [2] were no greater than 1-2%.
By extrapolation of the isochores to the vapor tension curve we determined the saturated vapor pres-
sure p v (Table 1). The same table gives the heats of sublimation of solid UF6 calculated from the Clapeyron
?Clausius curve, using Eq. (1). The errors in the values of r are less than 0.7%; the values average 1-2%
lower than those of [3].
Since the range of parameters of state under consideration lay in a region remote from the critical
point [4], the experimental p-p -T data obtained for gaseous UF6 were approximated by an equation which,
in contrast to the equation of state in the region close to the critical point [4], contained only the first
term with respect to density
z=
PI-L
=1.+B (T)p.
pRT
(2)
In this case the coefficient B(T) is identical with the second virial coefficient.
The following are the values of the second virial coefficient calculated by the method of least squares,
using an electronic computer (the error is ?4%);
T0, K
320
330
340
350
360
370
?B, cm3.g
2.93
2.73
2.51
2.31
2.15
2.05
The equation of state of UF6 finally takes the form
2.197.103 ) (3)
pillpRT =1+ (3.94
The mean deviation between the experimental data and those calculated from Eq. (3) never exceeds 0.2-0.3%
over the whole range of parameters of state studied.
The second virial coefficient values obtained from the present investigation and [4] were approximated
by a Lennard?Dyson potential. The calculated values of the intermolecular parameters of UF6 were e/R
224?K, o- = 8.3 A.
In conclusion, the author wishes to thank Academician I. K. Kikoin for advice and a number of use-
ful comments.
LITERATURE CITED
1. V. V. Malyshev, Teplofiz. Vys. Temp., No. 6 (1972).
2. B. Weinstock and R. Crist, J. Chem. Phys., 16, No. 5 (1948).
3. J. Masi, J. Chem. Phys., 17, No. 9 (1949).
4. V. V. Malyshev, At. Energ. , 32, No. 4, 313 (1972).
56
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Declassified and Approved For Release 2013/09/15: CIA-RDP10-02196R000400010001-9
SOME DOSIMETRIC MONITORING RESULTS AT THE
ITR-2000 NUCLEAR REACTOR IN SOFIA
I. T. Mishev and M. G. Gelev UDC 539.12.08:621.039.538.7
The basic biological shielding of the core of the IRT-2000 nuclear reactor in Sofia consists of water
and heavy concrete, as in other reactors of its type. In addition, in addition to the experimental channels
there is additional biological shielding consisting of water, paraffin, boric acid, and heavy concrete. Since
the thickness and the composition of this shielding vary in different experiments, the dose rate on the far
side of the shielding will also vary. As a rule, it will not be in excess of the maximum permissible dose
rate. Dos imetric monitoring in the main reactor hall is carried out with the aid of both stationary and
portable instrumentation capable of measuring the dose rate of y-radiation, fast neutrons E >0.5 MeV,
thermal neutrons E