SOVIET ATOMIC ENERGY - VOL. 38, NO. 5

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• Document Page Count: 113
• Document Creation Date: January 4, 2017
• Document Release Date: September 25, 2013
• Sequence Number: 3
• Publication Date: November 1, 1975
• Content Type: REPORT

? ,
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Russian Original Vol. 38, No. 5 May, 1975
November, 1975
SATEAZ 38(5) 361-468 (1975)
SOVIET
ATOMIC
ENERGY
ATOMHAFI 3HEPIMA
(ATOMNAYA iNERGIYA)
TRANSLATED FROM RUSSIAN
(C"
CONSULTANTS BUREAU, NEW YORK
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SOVIET
ATOMIC
ENERGY
Soviet Atomic Energy is abstracted_ or in-
dexed in Applied Mechanics Reviews, Chem-
ical Abstracts, Engineering Index, INSPEC?
Physics Abstracts and Electrical and Elec-
, tronics Abstracts, Current Contents, and
Nuclear Science Abstracts.
Soviet Atomie Energy is a cover-to-,Cover translation of Atormaya,
Energiye, a -publication of the Academy,of Sciences of-the USSR.
An agreement With the Copyright Agency of the USSR (VAAP)
makes available both advancercoPies of the Russian journal and
original .glossy, photographs and artwork. This serves to decrease
the necessary time lag between publication .of the original ad
publication of the translation and helps th improve -the quality
of the latter. The translation began with the first issue of the
Russian journal.
?
Editorial Boa,rd.of Atomnaya Energiya:
Editor: M. D. Millionshchikov
Deputy Director
I. V. Kurchatov Institute of Atomic Energy
Academy of Sciences of the USSR
Moscow, yssR
Alsociate Editor: N: A. Vlasov,
? A. A. Bochvar
N. A. bollezhar
V. S. Fursov
I. N. Golovin
V. F. Kalinin
' A. K. Krasin
V. V. Matveev-
M.
M.G. Meshcheryakov
palei
V. B. Shevchenko
V. I.-SMirnov
A. P. Vinogradov
A. P. Zefirov
Copyright C) 1975 Plenum_PublishingCorporation, 227 West 17th Street, New York,
-N.Y. 10011. All rights reserved. No article contained herein may be reproduced,
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Published monthly. Second-class postage paid at Jamaica, New York 11431.
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SOVIET ATOMIC ENERGY
A translation of Atomnaya Energiya
November, 1975
Volume 38, Number 5
May, 1975
CONTENTS
Engl./Russ.
OBITUARY
Vitalii Vasil'evich Shipov
361
282
ARTICLES
Neutron-Absorption Analyzer of Boron in the Coolant of the Primary Circuit of Water-
Cooled Water-Moderated Power Reactors ? V. P. Bovin, V. L. Chulkin,
and S. V. Shagov
363
283
BOOK REVIEWS
D. A. Kozhevnikov. Neutron Characteristics of Rocks and Their Applications in Oil and
Gas Geology ? Reviewed by E. M. Filippov
367 .
286
ARTICLES
Mathematical Model for Determining Unit Powers of Atomic Power Plants and Various
Reactor Assemblies ? V. M. Chakhovskii and V. V. Matskov
369
287
Absorption of Thermal Neutrons in Media with Localized Inhomogeneities
? A. V. Stepanov
374
291
Experimental Study of Neutron Thermalization by the Pulsed-Source Method
? A. Stanolov and V. nristov
379
295
Gamma Spectrometry and Metallography of the Fuel Elements in the Working Cassette
of the IVV-2 Reactor ? V. V. Bychenkov, V. I. Zelenov, S. G. Karpechko,
E. N. Pankov, and A. N. Timokhin
383
299
BOOK REVIEWS
I. S. Krashemikov, S. S. Kurochkin, A. V. Matveev, et al. ModernNuclear Electronics.
Vol. 1. Measuring Systems and Instruments ? Reviewed by I. V. Shtranik
388
303
ARTICLES
Change in the Structure of Carbon Materials under Neutron Irradiation
? Yu. S. Virgirev, I. P. Kalyagina, T. K. Pekal'n, and T. N. Shurshakova . .
390
304
Certain Laws Regarding Transient Radiation-Induced Creep in Construction Graphite
? Yu. S. Virgil'ev
396
309
Creation of a Standard Neutron Source (Field) at the I. V. Kurchatov Institute of Atomic
Energy ? R. D. Vasil'ev, N. B. Galiev, V. P. Yarina, E. N. Babulevich,
A. A. Kononovich, M. G. Mitel'man, N. D. Rozenblyum, Yu. M. Shipovskikh,
A. G. Inikhov, and V. I. Petrov
401
313
Radioactive Contamination of the Water Environment and Measures for Its Reduction
?L. I. Gedeonov, L. M. Ivanova, B. A. Nelepo, and A. G. Trusov
405
317
BOOK REVIEWS
R. E. Uhrig. Random Noise Techniques in Nuclear Reactor Systems ? Reviewed by
L. V. Konstantinov
411
323
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CONTENTS
ABSTRACTS
Some Regimes of Hydraulic Instability in the First Circuit of a Fast Reactor
(continued)
Engl./Russ.
? I. A. Kuznetsov.
413
325
Determination of the Nonhermeticity of a Type IRT-M Fuel Assembly in the Core of a
Reactor ? 0. F. Gusarov
414
325
Determination of "Synthetic" Scattering Cross Sections of Slow Neutrons for
Approximate Equations of Thermalization ? N. I. Laletin
415
326
Radial Distribution of an Electron Stream From a Monodirectional Point Source
?A. M. Kol'chuzhkin and A. V. Plyasheshnikov
416
327
Output Current of an Evacuated Direct-Charging Detector ? G. V. Kulakov
417
328
Chlorination of Uranium and Plutonium Oxides in Molten Chlorides of the Alkali and
Alkaline Earth Elements ? M. P. Vorobei, A. S. Bevz, and 0. V. Skiba
419'
329"/
Thermal Stability of Cesium Uranyl Tetrachloride on Heating in Air to 1000?C
? M. P. Vorobei, A. S. Bevz, and 0. V. Skiba
420
330
LETTERS TO THE EDITOR
Gas Cleaning Test Using a Ceramet Filter in Fluidized Bed Dewatering and Calcining
Waste Solutions ? N. S. Lokotanov and 0. A. Nosyrev
421
331
Protection of Stainless Steel against Interaction with Beryllium ? R. M. APtovskii
and E. A. Vasina
424
333
Validity of the Hypothesis of Hardening in Calculations of Creep of Irradiated Structures
? V. N. Kiselevskii, B. D. Kosov, N. P. Losev, D. V. Polevoi, B. V. Samsonov,
and N. Yudino
427
335
Effect of Reactor Radiation on the Thermoemf of Chromel?Alumel and Chromel?Copel
Thermocouples ? M. N. Korotenko, S. 0. Slesarevskii, and S. S. Stel'makh . . .
429
336
Cathode Sputtering of Niobium and Its Alloys in a Helium Glow Discharge
? D. M. Skorov, B. A. Kann, V. B. Volkov, P. I. Kartsev, and N. M. Kirilin .
431
338
Radioactive Impurities in Semiconducting Germanium ? A. A. Pomanskii
and S. A. Severnyi
433
339
Determination of Epithermal Neutron Spectra for Resonance Detectors by the Cadmium
Ratio ? R. D. Vasil'ev and V. P. Yaryna
435
340
INFORMATION: CONFERENCES AND MEETINGS
International Conference: "Advanced Reactors: Physics, Economics and Design"
? L. A. Kochetkov
437
342
Soviet?American Seminar on Steam Generators for Fast Reactors ? P. L. Kirillov.
441
3444
Fourth Symposium of the International Agency on Atomic Energy on Thermodynamics of
Nuclear Materials ? 0. S. Ivanov and A. S. Panov
)46
347"
Intense Fluxes of Fast Particles for Thermonuclear Devices ? N. N. Semashko
ll'i448
348
Conference on Applied Superconductivity ? E. Yu. Klimenko
451
350
Regular Session of Technical Committee 45 of the IEC ? V. V. Matveev
and L. G. Kiselev
455
353
The First Asiatic Regional Congress on Radiation Protection ? E. D. Chistov
458
354
INFORMATION: SCIENTIFIC-TECHNICAL COMMUNICATIONS
Soviet Specialists on Gas-Cooled Reactors Visit Switzerland ? I. Kh. Ganev
460
355'
INFORMATION: EXHIBITIONS AND SEMINARS
The Exhibition "Radioisotope Technology in the Complex Automation of Industry"
? K. A. Nekrasov
462
357
Seminars and Exhibitions of the All-Union Society "IZOTOP"
465
358"?
INFORMATION: CORRESPONDENCE
Startup of Cyclotron in Finland ? L. G. Zolinova
467
359
The Russian press date (podpisano k pechati) of this issue was 4/23/1975.
Publication therefore did not occur prior to this date, but must be assumed
to have taken place reasonably soon thereafter.
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OBITUARY
VITALII VASIL'EVICH SHIPOV
Vitalii Vasil'evich Shipov, Director of Atomizdat and member of the Communist Party of the Soviet
Union, passed away on April 22 after a prolonged illness.
V. V. Shipov was born in Moscow on April 12, 1911. After finishing his studies at the institute, he
occupied the position of Chief Engineer of the Central Telegraph of the Buryyat-Mongol Autonomous
Republic and then the post of Senior Engineer and Head of the Administration of the Main Communication
Lines of the Ministry of Communication of the USSR.
Since 1949, V. V. Shipov combined his regular work with editorial activities. He was the Director
of the Editorial Division of Svyazlizdat, Editor of the journal Sovetskii Svyazist, and the Director of
Svyaz'izdat. Vitalii Vasil'evich Shipov was intimately associated with the formation of the Atomizdat
where he continued to work until his last moments of life. While acting as Director of the Atomizdat,
Vitalii Vasil'evich carried out important work in smoothing out the editorial process, the preparation,
publication, and dissemination of literature on atomic science and engineering.
As Chairman of the Editorial Committee of the Atomizdat, V. V. Shipov took pains to establish a
wide authorial base for the Publishing House, and was instrumental in creating various Sections and
Branches of the Editorial Committee through which the scientific community could participate in selecting
and evaluating the submitted papers. He authored many popular science booklets and articles in periodi-
cal publications.
V. V. Shipov was a member of the Union of Journalists of the USSR and actively participated in its
work as Deputy Chairman of the Section of Editorial and Publication Workers of the Moscow Division of
the Union of Journalists.
For several years V. V. Shipov acted as a Member of the KuibyshevRegional Committee of the
Communist Party of the USSR and was elected Deputy of the Kuibyshev District Soviet. He was awarded
the order for Valiant Labour in the Great Patriotic War, the anniversary medal "For Valiant Labour.
In Commemoration the 100th Anniversary of the Birth of V. I. Lenin," the Gold and two Silver Medals
Translated from Atomnaya Energiya, Vol. 38, No. 5, p.282, May, 1975.
0 1975 Plenum Publishing Corporation, 227 West 17th Street, New York, N.Y. 10011. No part of this publication may be reproduced,
stored in a retrieval system, or transmitted, in any form or by any means, electronic, mechanical, photocopying, microfilming,
recording or otherwise, without written permission of the publisher. A copy of this article is available from the publisher for $15.00.
361
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of the Exhibition of Achievement of the National Economy of the USSR, badges for Excellent Work in
Publishing and for Distiguished Service in Civil Defence, a Diploma of the Presidium of the Supreme
Soviet of the Buryat-Mongol Autonomous SSR, and other decorations.
For his outstanding contributions to the book publishing trade, V. V. Shipov has been given the
honorary title of "Distiguished Worker of Culture of the RSFSR."
In all his professional and public activities, Vitalii Vasil'evich was noted for his communist prin-
ciples, calm efficiency, professional skills, vitality and optimism, kindness and exactingness in work,
competent leadership, and patience and persistence in educating his staff.
The great conviction, diligence, and modesty of Vitalii Vasil'evich always served as an example to
all his collaborators.
The memory of Vitalii Vasil'evich will for ever remain in our hearts.
362
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ARTICLES
NEUTRON-ABSORPTION ANALYZER OF BORON IN THE COOLANT
OF THE PRIMARY CIRCUIT OF WATER-COOLED
WATER-MODERATED POWER REACTORS
V. P. Bovin, V. L. Chulkin, UDC 621.039.562.2:621.039.562.26
and S. V. Shagov
Boric acid, added to the primary-circuit coolant of water-cooled, water-moderated power reactors
(WWPR) for reactivity compensation, improves the energy release distribution in the core, improves
the uniformity and depth of fuel burnup, and speeds up the reactor power operating conditions without
affecting safety [1].
The advantages of boron control can be most fully utilized by monitoring boron concentration at
various points of the circuit, in the purging and feed systems, and in the boric acid preparation units.
Chemical methods of analysis requiring sampling provide delayed information and do not reflect
the dynamics of processes taking place in the reactor circuit.
Neutron-absorption methods used for the determination of elements with high thermal-neutron ab-
sorption cross sections, including boron, are now becoming very popular [2, 3]. The design of boron con-
centration meters for WWPR has been reported in [4, 5]. As a rule, special measuring chambers or
lines which sample the coolant are used to provide optimum conditions for the measuring instrumentation.
Fig. 1
Circui 2
Fig. 2
Fig. 1. Count rate of a slow-neutron detector as a function of boron concentra-
tion with the detector and source located at the pipe center (NO and on the sur-
face (N2).
Fig. 2. Location of surface detectors of the boron analyzer on the primary-
circuit piping of a WWPR: 1) neutron counter, 2) steam generator, 3) detector,
4) neutron source, 5) measuring panel, 6) potentiometer recorder, 7) WWPR.
Translated from Atomnaya Energiya, Vol. 38, No. 5, pp. 283-286, May, 1975. Original article
submitted April 15, 1974.
0 1975 Plenum Publishing Corporation, 227 West 17th Street, New York, N.Y. 10011. No part of this publication may be reproduced,
stored in a retrieval system, or transmitted, in any form or by any means, electronic, mechanical, photocopying, microfilming,
recording or otherwise, without written permission of the publisher. A copy of this article is available from the publisher for $15.00.
363
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1120
7
2
Pu-Be source?
compensation channel
-CI II 13
1800V 12V
,0
Fig. 3.
10 20 JO 40
Fig. 4
50
Fig. 3. Block diagram of boron analyzer: 1) main counter SNM-16. 2) main detector,
3) stand-by SNM-16 counter, 4) compensation detector, 5) pipe with measured boric
acid solution, 6) pulse amplifier, 7) threshold circuit, 8) shaper, 9) remote calibra-
tion control circuit, 10) counter and amplifier power supplies, 11) analog time inter-
val meter, 12) computer, 13) potentiometer recorder.
Fig. 4. Count rate of SNM-16 counters as a function of H3B03 concentration, and cali-
bration curves of the time interval meter on all three ranges (1-3).
However, of most interest are methods and instruments for continuous on-line analysis of boron
concentration which can be applied without affecting the pipeline network.
Two measuring methods can be used depending on the piping diameter and boron concentration:
either counting of neutrons transmitted through a layer of the analyzed fluid, or counting reflected thermal
neutrons. The first method is suitable for measuring boron concentration in small diameter piping. The
second method can be used for boron analysis in a wider range of concentrations and in larger pipes (60
mm or more), the sensitivity of the method increasing with the diameter of piping up to about 100 to 150
mm and then remaining constant.
Figure 1 shows the neutron count rate as a function of B203 concentration, the Pu-Be source of fast
neutrons with a yield of 5 ? 106 neutr./sec and the thermal neutron counter (3He filled SNM-16 detector)
located on the surface and in the center of a 200 mm pipe. The count rate of reflected neutrons on the
pipe surface decreases approximately by one order of magnitude. The loss of sensitivity caused by this
geometry can be partially (approximately 1.5 to 2 times) compensated by placing both the counter and the
source in a reflector (water or paraffin) or by using a source with a higher yield of neutrons. In addition,
the application of high-efficiency, helium filled slow-neutron counters provides the necessary analytic
accuracy with Pu-Be neutron sources with a yield of 5 ? 106 neutr./sec.
In measuring the boron concentration in the primary circuit coolant one must take into account the
possibility of errors caused by the variable background due to delayed neutrons produced in the decay
364
WWPR- -
Boron input _,.6
Coolant outlet
Fig. 5. Schematic drawing of detector mounting for measuring boron concentra-
tion in the purging?feeding system of the primary circuit and in emergency shield-
ing tanks of a WWPR : 1) submersible boron-analyzer counter, 2) emergency H3B03
supply tank, 3) valves, 4) steam generator, 5) main circulating pump, 6) surface
boron-analyzer detectors, 7) feed pump, 8) purging circuit pump, 9) heat exchanger,
10) ion exchange filters.
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TABLE 1. Analyzer Calibration Results
11,B0.3 con-
centration,
g/kg
Count rate at
the main
channeloutput,
pulses/sec
H3 03 con-
centration,
g/kg
Count rate at
the main
Channel out-
put, pulse/tee
0
3042
4,77
2737
0,93
2965
7,99
2620
1,98
2891
11,4
2517
2,91
2831
14,0
2470
3,9
2773
50
2130
of fissionable elements and 17Na. This background decreases appreciably several tens of seconds after
the coolant leaves the core. If the necessary delay cannot be provided before analysis, the variable
neutron background should be compensated in the measuring apparatus.
On the basis of these considerations we have designed a neutron-absorption boron concentration
analyzer fitted with measuring and compensation detectors mounted side by side on the pipe surface
(Fig. 2) . Both detectors are structurally identical each containing two neutron counters, one operating
and one stand-by, with the neutron source between them.
The compensation detector, which counts the background of delayed neutrons in the coolant, has no
isotopic source. To improve sensitivity the detectors are provided with reflectors consisting of a stain-
less steel jacket filled with water. In operation on pipes carrying hot coolant, the reflector is used for
cooling the counters and is connected to a circulating water system.
Periodical checking of the system operation is enabled by placing the counters into rotating cadmium
shields with windows which can be remotely positioned to face the neutron reflector (reference point) or
the analyzed solution (reading). Testing can also be provided by periodical connection of the stand-by
counter.
It has been found that in this method of counting, the count rate of the main detector N less the count
rate of background pulses due to delayed neutrons and the neutrons entering the counter without passing
through the analyzed layer is inversely proportional to boric acid concentration C:
kC = N? ? ?1? QNn ? 1,
N -
where k is a proportionally factor, No is the pulse count rate of the main detector at zero boric acid con-
centration minus background pulses, and Q = 1/N is the average interval between pulses.
Figure 3 shows the block diagram of the boron concentration meter. Pulses from the neutron coun-
ters are transmitted through a 100-200 m long cable and matching transformer to the measuring panel
which has main and compensation channels. Each channel contains an amplifier, a threshold stage for
noise suppression, and a pulse length and amplitude shaper.
Boron concentration is measured by an analog computing circuit consisting of a time interval meter
with a linearized sensitivity characteristic [6]. The average time interval between pulses is determined
by charging an integrating capacitor Ci, connected between the input and output of a dc operational ampli-
fier, with a constant current and by discharging this capacitor by pulses N from the detector. The con-
stant background is compensated by a feedback circuit through which the integrating capacitor is charged
by a current inversely proportional to the output voltage. Solid-state integrated circuitry is used.
The analyzer has been designed to measure boric acid concentrations up to 50 g/kg and is provided
with three ranges: 0-10, 0-20, and 0-50 g/kg. The measured results are applied toapotentiometer re-
corder and to a control and computing circuit. The accuracy is better than 4% of full range for time inter-
val meter time constant T = 50 sec. Figure 4 shows the analyzer calibration for type SNM-16 counters and
the time interval meter response on all three measuring ranges.
A model of the instrument was tested at the Novovoronezh Atomic Power Plant. The detectors were
mounted on the purging water line of the primary circuit of the VVER-440 water-cooled water-moderated
power reactor following the heat exchanger and the water purification filters. The delayed-neutron back-
ground is practically zero at this point (about 7 pulses/sec) as it takes two minutes for the solution to
pass from the reactor to this point. The compensation detector can thus be disconnected and used as a
stand-by detector and for cases of emergency or fuel element leakage. The constant background in the
main channel, due to neutrons that did not pass through the moderator, was 1500-2000 pulses/sec and
365
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was compensated by feedback in the time interval measuring circuit thus providing a linear relationship
between the output voltage or current and the boron concentration.
Table 1 shows the results of analyzer calibration in the boron acid concentration range up to 50 g/kg.
The operation included a check of the long-term reproducibility of results (after more than three
weeks). The standard deviation of the obtained results 6 = 1/V2NT did not exceed 2%. Other detector
types as well as other mounting points can be employed depending on the measuring conditions (Fig. 5).
Submersible detectors are especially suitable for measuring boric acid concentration in solution
preparation tanks. Neutron sources with a yield of 5 ? 105 neutr./sec are sufficient for this purpose [6].
LITERATURE CITED
1. Operation of Reactor Facilities of the Novovoronezh Atomic Power Plant [in Russian], Atomizdat,
Moscow (1972).
2. Yu. G. Fadeev and F. A. Sychev, in: Nuclear-Physics Methods of Analysis [in Russian], Atomizdat,
Moscow (1971), p. 304.
3. M. A. Belyakov and P. V. Anchevskii, in: Nuclear-Physics Methods of Analysis [in Russian],
Atomizdat, Moscow (1971), p. 156.
4. K. Fahrman and F. Japel, Kernenergie, 10, No. 11, 337 (1967).
5. R. Gopal, Trans. Amer. Nucl. Soc., 13, No. 1, 237 (1970).
6. V. P. Bovin et al., in: Radiation Engineering [in Russian], No. 11, Atomizdat, Moscow (1975),
p. 263.
366
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BOOK REVIEWS
D. A. Kozhevnikov
NEUTRON CHARACTERISTICS OF ROCKS AND THEIR
APPLICATIONS IN OIL AND GAS GEOLOGY*
Reviewed by E . M. Filippov
The book discusses one of the most important and timely topics: the energy, spatial, and time dis-
tribution of neutrons and capture y quanta, and the measuring techniques used for the evaluation of neutron
properties of rocks as applied to problems in oil field geophysics.
In the first chapter the author gives a simple and clear classification of neutron techniques, considers
the scope of their application, and mentions the problems they are used to solve. This is followed by an
exposition of nuclear properties of rock forming elements and of impurity elements having anomalous
neutron properties. The chapter ends with a description of radioisotopic neutron sources. Here, and not
in the second chapter, is the proper place to discuss californium sources which are now finding wide appli-
cation in nuclear geophysics.
The second chapter is devoted to neutron moderation processes in rocks and describes elastic and
inelastic neutron scattering, various simple methods of calculating the spatial and energy distribution
of neutrons in rocks, and the effect of neutron absorption on their energy distribution. The concluding
sections of this chapter contain a discussion of the time distribution of moderated neutrons provided by a
pulse source and the relationships describing neutron moderation.
The age of neutrons, which is one of the most important characteristics of the spatial energy distri-
bution of moderated neutrons, is discussed in the third chapter which also includes rules for calculating
this parameter with various degrees of accuracy. The rules give results in good agreement with experi-
mental data. Together with neutron age, the author discusses neutron migration using the term "neutron
migration area" (pp. 74, 75). Actually, however, the discussion here concerns the square of this quantity,
the term "area" being entirely inappropriate in this connection. The same can also be said about the
migration length of y radiation produced by radiative neutron capture (p. 105). If the term was adopted
from literature this should have been stated explicitly and justified from a physical point of view. More-
over, similar quantities should have been termed uniformly: the squared diffusion length (p. 109) should
rather be called the diffusion area.
The process of thermal neutron diffusion in matter is discussed in the fourth chapter. The energy
spectrum of thermal neutrons is given, as is their spatial and space-time distribution and their radiative
capture. Techniques are described for measuring the diffusion characteristics and their magnitude.
In the fifth chapter the author considers the possibilities of neutron methods in solving practical
problems of oil and gas field geophysics and the nature of the dependence of NGM and NNM readings on
the stratum porosity m. The author favors the E. . Yu. Mikolaevskii formula and does not mention the
relation Jny = a + b In m, where a and b are constants, which is most frequently used in practice. It
would be desirable to discuss this relation in detail and compare it with the one cited in the book.
It would be more appropriate to discuss the problems associated with the effect of borehole radiation
of NGM readings and methods of INNM measurement in the preceding chapter as they do not directly relate
tothe discussed problem. This is especially true of the material associated with the determination of dif-
fusion parameters T and D. The material presented in pp. 159-163 partly repeats the text in pp. 101-102.
It can be stated in conclusion that the book concerns itself mostly with the theory of neutron methods
(chapters 2-4). Neutron properties proper are basically discussed in chapters 3-5, but even here they are
* Izd . Nedra, Moscow (1974). 184 pp.
Translated from Atomnaya Energiya, Vol. 38, No. 5. p. 286, May, 1975.
? 1975 Plenum Publishing Corporation, 227 West 17th Street, New York, N.Y. 10011. No part of this publication may be reproduced,
stored in a retrieval system, or transmitted, in any form or by any means, electronic, mechanical, photocopying, microfilming,
recording or otherwise, without written permission of the publisher. A copy of this article is available from the publisher for $15.00.
367
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for the most part treated rather schematically. For example, the methods of measuring diffusion charac-
teristics, discussed in Chapter 4 (pp. 113-120), are only briefly described which is typical of theoretical
courses. To make practical use of the described methods experimenters must turn to original works. This
holds, for example, for the techniques proposed by V. V. Miller and Yu. S. Shimelevich, as well as for
other techniques.
Thus, the book should have been more appropriately titled 'Principles of the Theory of Neutron
Methods as Applied to Oil and Gas Field Geophysics."
It can be stated in conclusion that the book is written in a clear language and is held on a high scienti-
fic level. It is very useful for geophysicists engaged in oil and gas prospecting and for nuclear geophysicists
,.specializing in engineering, mining, and coal prospecting geology. A reader interested in the development
and practical application of neutron methods will find the book most useful.
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ARTICLES
MATHEMATICAL MODEL FOR DETERMINING UNIT
POWERS OF ATOMIC POWER PLANTS AND
VARIOUS REACTOR ASSEMBLIES
V. M. Chakhovskii and V. V. Matskov UDC 621.311.2:621.039+001.58
There, is still no firm stand as to the unit powers of atomic power plants and reactor assemblies
using various reactor types to be put into operation till the year 2000. The need for a firm stand in this
respect becomes clear if one considers that very large amounts of electric power, up to several gigawatts,
are to be annually added till the end of this century. It is quite obvious that the realization of high-power
units meets with many difficulties which have been covered in considerable detail in [1-5].
In solving this problem it is necessary to give due consideration to unit power levels economically
feasible both in the immediate and the more distant future, and, on the other hand, to begin immediately
the determination of such levels in a proper sequence so as to ensure a rational allocation of the available
financial and manpower resources.
An estimation of the development of nuclear power engineering in the next 30 years requires the
knowledge of the limits of optimum plant size and of economically warranted power levels. In addition,
it is necessary to evaluate the most convenient from a technological and economical point of view,unit
power levels of nuclear power plants within the scope of future power developments and also the terms
when these new powerlevelsareput into practice.
This problem must be considered and solved in parallel with the progress in conventional power
engineering.
In this article the problems are solved with the aid of a dynamic optimization model. The main pro-
positions of this model are:
1. The dynamics of growth of the total energy and of the power of thermal and atomic power plants
individually is known. The growth of thermal and atomic plant powers are specified in terms of the num-
ber of hours of utilization.
2. Information on the fuel-energy balance is used to find the amount of each kind of fuel of thermal
power plaiiii71-iich can be used for a given price per 1 ton of nominal fuel at point of use. Resources of
fuel are divided in categories according to cost, the most cheap fuel being used first.
3. The transportation costs of nuclear fuel raw materials, and used up fuel elements are not taken
into account. The expenditure on fuel and its transportation for organic-fuel power plants are taken into
account according to the cost of mineral fuel at the point of use.
4. The cost of nuclear fuel and its cycling are deter-
mined in accordance with the type of atomic power plant.
The consumption of fuel for any specific reactor type is
assumed to remain fixed throughout the entire period of
calculation. Reserves of natural uranium also are clas-
TABLE 1. Predicted Growth of Unit Power
of Generating Units of Atomic and Thermal
Power Plants in the USA
Number of units
1980 1990
Unit power of generatiing
unit, MW
601-1200
1201-1800
1801-2400
2401-3000
APP
TPP I
APP
TPP sified into categories depending on their costs, the cheap-
101
23
_
120
11
_
227
95
32
11
est being used up first [6,7].
185
60 5. The time interval in the period of calculations
21
is assumed as one year or more.
Translated from Atomnaya Energiya, Vol. 38, No. 5, pp. 287-290, May, 1975. Original article
submitted May 16, 1974.
? 1975 Plenum Publishing Corporation, 227 West 17th Street, New York, N.Y. 10011. No part of this publication may be reproduced,
stored in a retrieval system, or transmitted, in any form or by any means, electronic, mechanical, photocopying, microfilming,
recording or otherwise, without written permission of the publisher. A copy of this article is available from the publisher for $15.00.
369
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Declassified and Approved For Release 2013/09/25: CIA-RDP10-02196R000400050003-3
6. The capital investment distribution over the years of power plant construction is allowed for by
a resources-freezing coefficient throughout the construction period.
7. The reserve power is calculated on the basis of installed power-plant power at the beginning of the
calculations eriod and taking into account the assumed growth of power in power systems.
8. The power of individual atomic and thermal ower plants is assumed to remain constantrozer
indefinitely long periods of time. Physically aging plants are replaced by equivelant ones (direct conver-
sion). Atomic and thermal power plants put into operation during the calculations period are assumed to
be utilized for a fixed number of hours at installed power throughout their entire exploitation period.
As input information to the model we use XAPP, Xt9T/PP( = 1. 2,..., 0; 1 =1, 2, ...,L) the
41
total power of atomic (APP) and thermal (TPP) plants respectively, fed in the interval 4 the number of
utilization hours being 11/; Gs(s = 1, 2,..., S) the amount of nuclear raw material received from the sources
at the price of natural uranium s; Bz (z = 1, 2, ..., Z) the amount and kind of organic fuel used by thermal
plants at the cost z per 1 ton of nominal fuel; Wa (c1 = 1, 2, ? ? ? ,Q) the electrical power of the q-th construc-
tion site, M.6,(4 = 1, 2, ...,0) the number of production workers engaged in electrical plant construction in
the interval 4; /\ 4(4 = 1, 2 ..... 0) the number of production workers engaged in operating the power plants
put into operation in the interval 4; max , max X. = 1, 2, ..., I; j = 1, 2, J; =1, 2, ..., 4) the
319T
maximum possible production power of known types of respectively atomic and thermal power plant units
in the interval of the calculations period (I, J is the number of typical sizes of atomic and thermal power
plants respectively).
The above conditions can be formulated mathematically as follows. We have to find
QL SI
1111I EE ,siaorti iaoN
8=i q=-1 1=1 371 -
z J
E E E jzionizioNj] (1 + p)r-i(}
3-1
0 I
4-p E (E E Yjo ) (1 p)T=t$,.
(1)
14v=1 i=1 j=1
Here 4 = 1, 2, .. 09 is the number of time intervals in the calculations period, AT is the interval of master-
ing type i, j plant; Eisio, Eiz/ j are the specific adduced expenditures of tower plants using nuclear and
organic fuel respectively with jpe i (j) units for a natural uranium price s and organic fuel price z, utilized
for III hours at installed power at the q-th construction site in the interval .6 of the calculations period;
these expenditures include the cost of distribution lines, power plant construction, and building; nisi",
nizico are the desired variables which determine the number of generating units of atomic and thermal
plants. The combination of subscripts (i, j, s, z, 7, q, 4) indicates the i-th (j-th) type-size of the unit,
s (z) is the type of fuel used with respect to its cost, h1is the number of hours of utilization at installed
power?, is the interval of the calculations period, Ni, Nj is the unit power of type i (j) atomic and ther-
mal power generating units in the interval ist; E P4T, E?j4T
is the cost of mastering a new type of atomic or
thermal generating unit put into operation at the beginning of AT; Y. , Y; g, is a Boolean variable (0 or 1,
i
LAT jeT
such that if Y. = 1 and Y. = 1' the unit can be introduced in the interval .6T (in the model)), p is a
147 J4T
standardizing factor allowing for the noncoincidence of the various expenditures, T is the year of expendi-
----- ?t)re adduction, t4 is the year preceding stage 4, and ti9T is the year preceding stage AT?
The minimum of function (1) is found under several constraints (either equalities or inequalities).
The first group of constraints expresses the necessity of providing a given volume of atomic and thermal
power inputs at all stages of the calculations period:
QS APP
E E E n81oNi(1---Pi)>X01
q=1 s=i 1=1
(=I,2,? ... 0; /=1, (2)
Q Z J TPP
E E E (1? Pi) >xo,
q=t z=1 i=t
? 1, 2 ?.0; / =1, 2..., (3)
where pi, pj is the specific reserve of type i (j) plant determined in accordance with the systematic propo-
sitions put forward in [8].
The constraints reflecting the limited amount of nuclear raw materials at a fixed natural uranium
price is written in the form
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QLI
E E E PtionivoNt+GL)