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SOVIET ATOMIC ENERGY VOL. 32, NO. 4

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CIA-RDP10-02196R000300100004-7
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December 27, 2016
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April 1, 1972
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Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Russian Original Vol. 32, No. 4, April, 1972 - rc Translation published November, 1972 SATEAZ 32(4) 303-434 (1972) SOVIET ATOMIC ENERGY ATOMHAFI 3HEP114F1 (ATOMNAYA ENERGIYA) TRANSLATED FROM RUSSIAN CONSULTANTS BUREAU, NEW YORK Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Dvot Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 SOVIET: ATOMIC ? ENERGY , ( So yie t Atomic Energy is a dover-to-cover translation of Atomnaya Energiya, a publication of-the Academy of Sciences of the USSR. An arrangement with Mezhdunarodnaya Kniga, the Sciviet book export agency, makes available both advance copies of the Rus- sian journal and original gloss,photographs and artwork. This serves to decrease the necessary time lag between publication of thee original and publication of the translation and helps to im- prove the quality of .the latter. The translation began with the'firat issue of the Russian journal. Editorial Board Atomnayl Energiya: Editor: M. D. Millionshchikov , . Deputy Director I. V. Kurchakay.?Institute of Atomic Energy . Academy Of Sciences of the USSR Moscow, USSR Associate Editors: N. A. Kolokol'tsov N. A. Vlatov A. A. tochvar N. A. Doliezhar ? Fursov I.N. Golovin V. F. Kalinin ' Krasin ,A. I. Leipunskii A. P. Zefirov V. V. Matveev M. G. Meshcheiyakov P. N. Palei ,V. B. Shevchenko D. L. Simorienko V. I. Smir'nov A. P. Vinogra'dov ? Copyright ?1972 Consultants Bureau, New York, a division of Plenum Publishing Corporation, 227 West 17th Street, NeW York, N. Y. 10011. AD rights 'reserved. No article contained, herein may be reproduced .for any purpose whatsoever without permission' of the publishers. Consultants Bureau journals' appear about six months after the publication of the original Russian issue. For bibliographic accuracy, the English issue published by Consultants Bureau carries the same number and date, as the original Russian from Which it was translated. For example, a Russian issue published In Decem- ber will appear in a Consultants Bureau -English translation about the following June, but the translation issue will carry the December date. When cirdering any ? volume or particular issue of a Consultants Bureau Journal, please specify the date and, where applicable, theyolume and issue numbers of the original Russian. The material you will receive will be a translation of that Russian volume or issue. Subscription $75.00 per volume (6 Issues) 2 volumes per year Single Issue: $30 Single Article: $15 (Add $5 for orders outside the United States end Canada.) ? CONSULTANTS BUREAU, NEW YORK AND' LONDON , 4 Published monthly. Second-class postage paid at JAMaica, New York 11431. 227 West 17th Street New York, New York 10011 'Davis House ' 8 Scrubs Lane Harlesden, NW10 6SE England Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100064-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 SOVIET ATOMIC ENERGY A translation of Atomnaya Energiya Translation published November, 1972 Volume 32, Number 4 April, 1972 CONTENTS Engl./Russ. On the Occasion of the Seventieth Birthday of Academician Viktor Ivanovich Spitsyn ? ? ? 303 267 RE VIEWS Problems if Safety of Nuclear Power Plants? V. A. Sidorenko 304 269 Peaceful Use of Atomic Energy and the Environment ? U. A. Israel 308 273 BOOK REVIEWS New Books 313 278 ARTICLES Antimony, Bismuth, Arsenic, and Other Elements in Ore Bodies and Haloes of a Uranium? Molybdenum Deposit ? G. I. Rossman, N. A. Stepanova, I. V. Sychev, and G. A. Tarkhanova 317 279 Radiation-Induced Growth of Polycrystalline a-Uranium ? M. A. Vorob'ev V. F. Zelenskii, E. A. Reznichenko, and A. S. Davidenko 323 287 Calibration of Gamma ? Gamma Densitometers ? K. Umiastowski 328 293 Neutron Diffusion in a Polarized Proton Medium ? Yu. N. Kazachenkov and V. V. Orlov 333 297 The Energy Lifetime and Diffusion of Particles in "Tokamak" Systems ? Yu. N. Dnestrovskii, D. P. Kostomarov, and N. L. Pavlova 337 301 ABSTRACTS Neutron Slowing-Down Theory in P2-Approximation of the Method of Spherical Harmonics ? I. A. Kozachok and V. V. Kulik 343 307 Multiparameter Optimization of Nuclear Power Station with Flash Desalination Facilities ? Yu. D. Arsen'ev, Yu. S. Bereza, S. V. Radchenko, and V. A. Chernyaev 344 308 Pseudoblind Startup of Nuclear Reactor ? B. G. Volik, T. A. Gladkova, and G. L. Polyak 345 308 Redistribution of Fuel in Irradiated Dispersion Type Fuel Elements ? L. M. Tuchnin and E. F. Davydov 346 309 The Neutron Radiation of Pu23802 Containing Different Amounts of 018 ? V. A. Arkhipov, G. V. Gorshkov, B. S. Grebenskii, B. A. Mikhailov, V. V. Fedorov, S. P. Khormushko, and A. A. Chaikhorskii 347 310 Magnetic Systems for the Transport and Accumulation of Slow Neutrons ? I. M. Matora and 0. A. Strelina 348 310 Thermodynamics of Formation of Plutonium Trichloride in a Fused Potassium Chloride Medium ? M. V. Smirnov, V. I. Silin, and 0. S. Skiba 349 311 Effect of Oxidation on Strength Characteristics of Graphite ? E. I. Kurolenkin, N. S. Burdakov, Yu. S. Virgil'ev, V. S. Ostrovskii, V. N. Turdakov, and Yu. S. Churilov 350 312 The Equation of State of Uranium Hexafluoride over a Wide Range of Parameters ? V. V. Malyshev 351 313 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 CONTENTS (continued) Engl./Russ. LETTERS TO THE EDITOR Experimental Study of the Performance of the RG-1M Geological Research Reactor - V. I. Alekseev, A. M. Benevolenskii, V. V. Kovalenko, 0. E. Kolyaskin, L. V. Konstantinov, V. A. Nikolaev, V F Sachkov, and A M Shchetinin ?,` . . M. A. , F. V. , , ,6 rface Contamination of VVR-M Fuel Elements by Fissionable Material and its Contribution to the Fragment Activity of the Coolant - N. G. Badanina, K. A. Konoplev, and Yu. P. Saikov Equipment for Study of Migration of Radioactive Products Along the Cross Section of 353 355 315 316 Fuel Element - A. V. Sukhikh, V. K. Shashurin, E. F. Davydov, and M. I. Krapivin 358 318 Vacuum-Cathode Etching of Uranium in VUP-2K Equipment - D. M. Skorov, A. I. Dashkovskii, V. V. Volkov, and B. A. Kahn 360 319 Change in the Structure and Properties of Titanium Carbide under the Action of Irradiation - M. S. Kovaltchenko, Yu. I. Rogovoi, and V. D. Kelim 362 321 Change in the Density of Single-Crystal Tungsten durineNeut'ron Irradiation - V. N. Bykov, G. A. Birzhevoi, and M. I. Zakharova 365 323 Some Principles of the Oxidation of Reactive Graphite - N. S. Burdakov and V. N. Turdakov 367 324 How Inorganic Electrical Insulating Materials are Used in Reactors - N. A. Aseev . . . 370 326 Neutron Diffusion in a Medium with Channels - N. I. Laletin 373 328 Recording of Acoustic-Emission Signals in Construction Elements - Yu. V. Miloserdin, V. M. Baranov, and K. I. Molodtsov 376 330 Determination of the Individual Fluxes of -y-Quanta and Neutrons by Means of a Thermoluminescent LiF Crystal - K. M. Kudelin 378 331 Experimental Determination of Sensitivity of Direct Charge Detectors in Thermal and Epithermal Region - N. D. Rozenbly-um, E. N. Babulevich, A. E. Alekseev, V. A. Zagadkin, V. S. Kirsanov, E. M. Kuznetsov, A. A. Kononovich, and M. G. Mitel'man 381 333 Gamma-Ray Detectors from i-Conductivity Germanium - V. S. Vavilov, L. A. Goncharov, T. I. Pavlova, Ya. Khurin, and M. V. Chukichev ...... . . 384 335 Germanium Radiation Counters as Charged-Particle Spectrometers - S. M. Ryvkin, V. V. Peller, N. B. Strokan, V. P. Subashieva, N. I. Tisnek, and V. K. Eremin 386 336 Neutron Radiation Standardization - V. G. Zolotukhin, I. B. Keirim-Markus, 0. A. Kochetkov, V. I. Tsvetkov, and V. Cherkashina 388 338 Calculation of the Concentration of fl-Active Gases Radiometrically Measured with a Cylindrical Counter - A. A. Gusev 391 340 Backscattering Coefficients for 12-25 MeV Electrons Incident Obliquely on Metallic Surfaces - V. P. Kovalev, V. P. Kharin, V. V. Gordeev, and V. I. Isaev . . . 395 342 Searches for Tracks of Fragments from the Spontaneous Fission of Far Transuranium Elements in Natural Minerals - 0. Otgonsuren, V. P. Perelygin, S. P. Tret'yakova, and Yu. A. Vinogradov 398 344 ,ve. sium Distribution in the Surface Layer of the Pacific Ocean - 0. S. Zudin, B. A. Nelepo, A. N. Spiring, and A. G. Trusov 402 347 Seasonal Extremes of Concentration of Nuclear Fission Products in the Atmosphere - A. E. Shem'i-zade 406 350 COMECON NEWS Agreement on Setting up the Interatominstrument Society - Yu. Yurasov 409 353 Collaboration Logbook 412 354 INFORMATION: CONFERENCES AND SYMPOSIA The Moscow Engineering and Physics Institute Scientific Conference - V. Frolov . . . . 414 357 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 CONTENTS Seventh All-Union Conference of Representatives of Four Nuclear Data Centers (continued) Engl./Russ. ? A. Abramov and V. Popov 417 359 The All-Union Conference on Plasma Theory ? I. P. Yakimenko 419 360 The Tenth International Conference on Phenomena in Ionized Gases ? P. P. Kulik 422 362 Dresden Conference on Mossbauer Spectroscopy ? A. M. Afanasiev 426 364 Warsaw September 1971 Symposium on Nuclear Electronics ? G. P. Zhukov, V. G. Zinov, I. F. Kolpakov, and A. N. Sinaev 429 365 IAEA Draft Regulations for Safe Transportation of Radioactive Materials ? S. Martynov. 431 367 V/O Izotop Agency Seminars and Exhibits 432 367 The Russian press date (podpisano k pechati) of this issue was 3/ 29/ 1972. Publication therefore did not occur prior to this date, but must be assumed, to have taken place reasonably soon thereafter. Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 ON THE OCCASION OF THE SEVENTIETH BIRTHDAY OF ACADEMICIAN VIKTOR IVANOVICH SPITSYN The editorial staff of Atomnaya t nergiya warmly greets Academician Viktor Ivanovich Spitsyn on the occasion of his 70th birthday, and wishes him excellent health, long years of life, and creative successes. Translated from Atomnaya Energiya, Vol. 32, No. 4, p. 267, April, 1972. 0 1972 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. 303 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 REVIEWS PROBLEMS OF SAFETY OF NUCLEAR POWER PLANTS* V. A. Sidorenko UDC 621.039.51 Problems of safety of nuclear power plants occupied one of the most prominent places among the sub- jects discussed at the IV Geneva Conference. Of 505 reports read at the Conference, 78 dealt with safety. In accordance with the topics they dis- cussed, these reports can be arbitrarily divided into five groups: 1. Discussion of the general scientific and engineering aspects of nuclear power plant safety including a study of the fundamental approach to safety control (so-called "philosophy of safety") (24 reports). 2. Legislation concerning safety, norms, standards, and legal problems associated with the division of responsibilities, etc., (nine reports). 3. Effect of nuclear power on the environment including a discussion of the actual conditions prevail- ing at nuclear power plant sites (23 reports). 4. Scientific and engineering problems associated with the removal of radioactive waste and its burial (eight reports). 5. Effects of radiation on living organisms, radiation protection and shielding (14 reports). Approximately the same attention has been devoted to two aspects of nuclear safety: the effect on en- vironment and handling of nuclear waste (3rd and 4th groups, 31 reports) and the scientific and engineering principles of nuclear plant safety and setting up norms for safety control (1st and 2nd groups, 33 reports). The materials presented at the Conference reflect considerable advances in nuclear safety control: the problem is now much better understood, technical and organizational measures of safety control have improved, and a reliable basis has been provided for nuclear safety taking into account the expected growth of nuclear energy. The expected growth of nuclear power focussed attention on the effect on the environment of nuclear ?engineering in general and of specific power plants whose operation proved the adequacy of the safety mea- sures provided. One conclusion that follows from the discussion is that the radioactivity level in the vicinity of nuclear power plants and fuel processing plants is very low and that the amount of radioactive waste is considerably less than allowed by national supervisory and legislative organs for every specific plant. De- tailed information on the environmental effects of atomic installations was presented in the American Report No. 087t, English Report No. 512, West German Report No. 399, etc. For example, the annual waste of radioactive materials of commercial nuclear power plants in 1970 in the USA amounted to 0.14-25% and 0.002-6.5% of the allowed level of liquid and gaseous waste (Report No. 087). Even now it is possible to design nuclear reactors with a radioactive waste level as low as desired. British experience indicates that fuel processing plants produce the greatest amount of radioactive waste. Many countries have undertaken special studies whose aim is the reduction of radioactive discharge from future high-output fuel processing plants. *Review of papers presented at the IV International Conference on Peaceful Uses of Atomic Energy, Geneva, 1971. t Lists of reports presented at the Geneva Conference were published in the October issues of Atomnaya Energiya (Soviet Reports) and Atomnaya Tekhnika za Rubezhom (foreign reports) in 1971. Translated from Atomnaya Energiya, Vol. 32, No. 4, pp. 269-272, April, 1972. Original article submitted January 13, 1972. 304 ? 1972 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 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 By considering the possible ways of penetration of radioactive products into the surroundings, and by comparing environmental pollution due to nuclear and fossil fuels, the authors of the Soviet Report No. 684 arrived at the conclusion that nuclear energy allows the conservation of a reasonably clean environment; what is more, replacement of fossile-fuel power by nuclear power should lead to a considerably lower level of contamination of the surroundings by toxic materials and so improve the environment. Despite the optimistic prospects of the present and future states of nuclear safety, all reports call for still more stringent measures to ensure the safety of nuclear power plants with respect to both "actual" and "potential" radiation dangers (reduction of allowed radioactive-discharge levels and improvement of the reliability of safety devices and radioactivity containment devices). This trend is associated with the ever increasing number of nuclear power plants and their location in densely populated areas. Perfection of safety systems, including containment devices, proceeds in the direction of higher de- vice efficiency and reduced size and cost. This is quite pressing as the rise in the cost of nuclear power plants is due largely to the additional safety measures necessary to meet the more stringent requirements. Another feature characteristic of modern trends is the increasingly important role of equipment re- liability in securing actual plant safety and in reducing the probability of accidents. Although these aspects of the problem of safety are not entirely new, they have become recently of primary importance together with safety measures that can be termed "obvious." Of independent significance is the supervision of plant equipment at all stages, from its manufacture to utilization. The accumulated operational experience helped to improve methods of continuous supervision and periodic inspection of nuclear plants (ultrasonic flaw de- tection, noise monitoring, etc.). As follows from the reports, particular attention is now devoted to specific solutions to key technolo- gical safety problems that are revealed in studies of the possible developments of dangerous processes in nuclear plants especially under emergency conditions. The basic trends in nuclear plant safety were discussed in USA reports (Nos. 038, 040) from the point of view of "protection in depth" which includes the following steps in the provision of nuclear safety: secur- ing equipment reliability, provision of technological and circuit impossibility of dangerous consequences of any single failure or damage, limitation of the consequences of any possible emergency case. The fact that problems of nuclear plants safety are complex and many-sided and have no single uni- versal solution has been stressed in many reports. In particular, one cannot expect that security can be provided only by high-quality equipment (much better than used in conventional power plants) or only by en- suring containment of the effects of possible emergencies (such as isolation of the plant). The problem must be considered from all its aspects. The implementation of the safety-in-depth principle can be seen in the different approaches to nuclear plant safety. In one of the possible variants all systems and equipment of the plant are divided into three functional parts: the reactor proper, equipment and systems that ensure its normal operation; "external" protection systems that reduce the possibility of hazardous deviation of plant parameters from their design values and protect the plant in case of failure of normal operating devices; systems whose task is to reduce as much as possible the consequences of any potential accident. The safety of nuclear power plants is ensured by independent and reliable performance of all these three functional parts. In a different approach, safety-in-depth is ensured by different independent and reliable "barriers', that prevent penetration of fission fragments to inhabited areas: from the fuel to coolant, from the coolant to the reactor location, from the power plant location to the surroundings, and finally from the surround- ings by various means to the population. The development of specific concepts and criteria of safety in several countries merits special atten- tion. The desirability of a numerical and probabilistic approach to the evaluation and standardization of nuclear safety has been recently frequently stressed together with the fact that the amount of statistical data on the performance of nuclear power plant equipment is still insufficient. The expensiveness of putting this approach into practice and the importance of international cooperation for the solution of this problem has been pointed out in the French Report No. 579. The Conference proved beyond doubt that the necessity of a 305 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 numerical approach to safety analysis is now generally accepted, but that, at the same time, the feasibility of a probabilistic approach to safety standardization is still treated with reserve. Numerical methods of estimating equipment reliability and accident probability are quite advanced and should be widely used in design practice of nuclear power plants. These methods make it possible to compare various approaches and to select optimum solutions in the design of safety equipment and devices. However, there is apparent- ly no sufficient basis for a numerical treatment of the standardization of nuclear plant safety in the immedi- ate future. In the West German Report No. 364 attention is called to the fact that throughout a normal life span all existing nuclear power plants are unable to provide sufficient statistical data for very grave acci- dents whose probability is estimated as 10-7 per year; in such cases the numerical approach becomes mean- ingless. The most frequently used concept in safety control is still the concept of the "basic design accident." Perfection of this concept is partially evident in the fact that attempts are made to apply probabilistic meth- ods in selecting the basic design accident. One of the most important advances in this field is the use of not only "the maximum probable accident" but of a full spectrum of possible accidents of which the basic design accident is one. This is done in order to protect the plant not only against major but little probable potential dangers but also against real dangers presented by much more probable equipment failures. An effective and systematic approach to the analysis of the spectrum of emergency situations is the so-called "failure tree." This method reveals all situations that are liable to result from any specific failure or damage. The failure tree makes it possible to demonstrate and evaluate numerically various combinations of serious damages that can lead to an emergency situation. In aqueous reactors the basic design accident is still assumed to be the total disruption of the main pipeline of the circulating loop. The possibility of reactor vessel rupture is also considered. Some designs (e.g., in West Germany) even consider the probability of an accident involving vessel damage. The most probable location of vessel damage is considered to be the region where the circulating loop pipes are con- nected to the vessel. An analysis of the probability of crack development in the vessel makes it possible to take into account in the design defects in the vessel that can cause leakages much smaller than resulting from a burst in the main pipeline (West German Report No. 364). A modification of the basic design accident concept was described in the Canadian Report No. 150. The plant safety is evaluated by quantitatively analyzing the frequency of occurrence of probable hazardous pro- cesses in the system, but the use of specific maximum radiation exposure of the population is based on two principal schemes of accident occurrence: a single failure in standard technological equipment with the pre- servation of full capability of accident prevention and containment devices or the coincidence of failure of both the standard operating system and the accident prevention system. In the first case maximum radiation exposure is that acceptable for normal operation; the second case involves the use of special maximum radi- ation exposure rates. The available design and operational experience made it possible to find many specific solutions in various safety control systems (USA Report No. 040). For example, methods have been developed for the construction of equipment and buildings resistant to earthquakes (Japanese Report No. 226, Swiss Report No. 672), hurricanes, floods, and other natural disasters. There is also the experience of building a nu- clear power plant near an airfield where the danger of collision or fire caused by an airplane accident must be taken into account. Instruments and a program have been developed for monitoring the spread of radio- activity in the locality surrounding nuclear power plants. Devices have been developed for aqueous reactors which monitor and if necessary suppress effects associated with xenon power fluctuations (such as, for example, absorbing rods of partial length); fixed in- termitent absorbers are used for canceling the positive temperature coefficient of the moderator reactivity. Comprehensive programs have been developed for analyzing the vibrations of intravessel devices in the course of start-up tests for the detection and elimination of weak points. Specific solutions aimed at im- proving the construction reliability, provision of continuous and periodic supervision, and ensurance of operating efficiency under emergency conditions are incorporated in the design of reactor cooling systems, of buildings and containment installations, of safety control systems, monitoring and measuring apparatus, and other systems. Among problems that require further research are: development of flaws in steel structures of circulation loops; 306 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 thermal interaction of fuel and coolant, in particular the heat exchange crisis (British Report No. 477); embrittlement of thick steel samples (including thermal shock in case of emergency cooling of the re- actor core); performance of safety systems under emergency conditions; critical parameters and power (this can be said to be a "perennial" problem); the probability of natural phenomena which must be allowed for in the design of nuclear power plants; improvement of the safety systems of core cooling (USA Reports Nos. 040 and 039); conditions of heat removal in time of and after emergencies involving the loss of coolant; hydrodynamic effects in the reactor vessel and in the cooling loop in case of large leakages; improvement of remote monitoring methods of the equipment state in the course of reactor operation and perfection of ultrasonic methods; melting of the reactor core (West German Reports Nos. 365 and 364). Special attention has been devoted to the safety of fast-neutron reactors. In sodium-cooled fast reac- tors characteristic hazardous events in which a single failure or damage is liable to cause grave conse- quences are damages in the primary loop, sodium ignition, chain damage of fuel elements, the passage of large gas bubbles through the core, etc. Accordingly, in the analysis of various design accidents (fast re- activity buildup, stoppage of coolant circulation, etc.), and in the development of protective measures parti- cular attention was given to the study of such phenomena as the formation of voids in sodium, interaction of the coolant with molten fuel, the mechanism of the spread of fuel element damage, the Doppler effect, the formation and spread of aerosols in connection with sodium ignition (USA Report No. 041). In conclusion, one should stress once more the generally accepted importance of the creation of a system of norms and rules for all stages of the design, equipment manufacture, construction, operation, and maintenance of nuclear power plants. The reaction of such a system of norms and rules is a continuous process. Besides this work, which is conducted by the Atomic Energy Commission for the development of general rules, criteria, specifications, procedures, etc., with the participation of 1200 representatives of 400 organizations, work is going on in the USA on the creation of a system of 78 most important nuclear standards. The development is now being concluded of the first ten standards to which belong: secondary criteria for pressurized-water reactors; secondary criteria for boiling water reactors; criteria for taking into account seismic effects in the location and design of power reactors; qualification and training of nuclear power plant personnel; specifications of periodic test in nuclear power plants; specifications on prestart and startup tests of nuclear power plants; criteria and practical measures for securing quality performance of nuclear power plants, etc. One thousand and five hundred nuclear standards are to be developed in the next decade. Experience indicates that nuclear power plants can be and are designed to operate reliably and safely. The development and introduction into practical use of a system of norms and standards should consolidate the present level of technology and extend it successfully to other fields. 307 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 PEACEFUL USE OF ATOMIC ENERGY AND THE ENVIRONMENT* U. A. Izrael' UDC 621.039.77 With the rapid development of nuclear power engineering and a large-scale introduction of atomic energy in industry and daily life it is inevitable that mankind would be affected by nuclear radiation and radioactive products would get into natural media. These problems appear in the production of nuclear fuel and atomic power, in reprocessing fuel, and in handling wastes and isotopes. Numerous estimates show that by the year 2000 the generation of electrical power from atomic power plants (APP) will exceed 3 mill. MW and will comprise -50% of the entire electric power generation. At present the number of APP is increasing in many countries. One of the most important conditions for extending the network of APP consists in ensuring the safety of operation of these power plants from the point of view of the effect on the environment. Estimates show that the main source of radiation effect on man (at present and in future) is the con- tamination due to the production of atomic energy [1]. Besides, it is necessary to consider specific thermal contamination of the natural media in the operation of APP. A large attention is being devoted to these problems. The effect of radioactive contaminants on the environment is tieing investigated extensively and the problems appearing in these investigations are dis- cussed in international meetings and symposia [2, 3]. At the IV Geneva conference on the peaceful use of atomic energy many papers were devoted to this problem. In two meetings of the special section on "The effect on the environment and the reaction of the population" 12 papers (of which three were from Soviet authors) were read and in addition six papers (two by Soviet authors) were presented in abstract form. A number of papers, presented in other sections, were also related to this problem (for example, papers on working out the principle for locating APP and the choice of safe areas for APP). It was noted at the conference that the problems of the effect of radioacitve substances on man and the biosphere as a whole are focal in the peaceful use of atomic energy. It is clear from the papers presented at the conference that extensive investigations are being carried out in different countries on the possible ways of incidence of radioactive products into the environment and their interaction with the biosphere and the migration of isotopes to human body through different biological chains. On one hand careful measurements and study of the behavior of radioactive products penetrating into the environment from reactors and plants are being made; on the other hand the interaction of the radio nuclides with the natural media are being studied in a general way. The Soviet papers discussed in detail the results of the study of biological effect and behavior of radio- active products in agricultural cycles [4] and in forest plantations [5]. Extra-root entry of radio nuclides into plants and also their assimilation by plants from the soil and passage to livestocks is discussed. During global fall-outs of long-life radioactive products the maximum amount of radio nuclides is retained in agricultural plants. It is found that the maximum content of radio nuclides in harvest is ob- served after the period of formation of the productive organs (for example, the radio nuclide content in wheat is maximum when the wheat attains milk ripeness). *Review of papers presented at the IV International Conference on Peaceful Uses of Atomic Energy, Geneva, 1971. Translated from Atomnaya Energiya, Vol. 32, No. 4, pp. 273-277, April, 1972. Original article submitted January 31, 1972. ? 1972 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. 308 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 The assimilation of radio nuclides by agricultural plants from soil is characterized by the following figures: the contaminated area froni which the radioisotope is assimilated (per kg of the product) is hundreds of cm2 for Zr95, tens of cm2 for W185, a few cm2 for Cs137, Sr90, and Fe59, a few tenths or hundredths of cm2 for Ce144, Ru106, Zr95, and varies between a few tenths to a few thousandths of cm2 for PU239, 1J235, PM147 Y91. For extra-root incidence the radio nuclide content in a wheat grain is ten times higher than in the case of their assimilation from soil. In respect of the concentration in milk and meat radio nuclides form a descending series I"1 > Mo99 > Sr89 > Bat?. The limiting fall-out intensities of radio isotopes and their content in soil, at which the annual inci- dence of nuclides into human organism along with food does not exceed the limiting admissible value, are estimated as: for Sr" ?1.5 mCi /month ? km2 (content 2 Ci/km2), for 1131 ?0.5 mCi /day ? km2. It is shown that the main degree of radiational affliction of grain cereals is caused in the forming ears. The problems of migration of radio nuclides in forests, radiation decrease in forests and the effect of radioactive fall-outs on bio-organisms under the forest cover are discussed in [5]. The results of the investigations show that the forest, as a part of the landscape, is among one of the most sensitive biological systems to radioactive fall-out. The results of a 15 year study of the behavior of radio nuclides, falling into water and earth ecosys- tems during the operation of a reactor in model experiments at Oak Ridge laboratory in USA, are presented in [6]. For water systems the isotopes Sr", C sl", Co", and T3 (sometimes Ru'", Sb125, and Zn") are typical; for forest and field systems Co", Sr", Zn + Nb, Rolos, Cs137, and Ce144 are typical. The results of studies of dilution and diffusion of radio nuclides in sea water, and also of the possi- bility of incidence of these products in sea organisms (Co", Fe59, and Mn54) are presented in Indian [7] and Japanese [8] papers. The background radiation situation and also the dose from medicinal procedures in different countries are discussed in some papers. For instance, it is shown that the natural background from the radiation from mountain rocks and cosmic rays comprises 120 mrem/ yr [9]; the intake of radiation through medicine gives an average genetic dose of 20-37 mrem/ yr [9, 10], while the global fall-outs from the past tests of nuclear weapons give an average dose of 10 mrem/ yr [9]. The radioactive contamination of ocean waters and the behavior of some radio nuclides in sea water are estimated in a Soviet paper [11]. In 1966-1967 on the whole there was a decrease in the contamination of the surface waters of Pacific and Atlantic oceans. The amount of Sr", going deep into Pacific ocean, exceeds the fall-out during this period. Technogenic radioactive regions have been detected (for instance, near the west coast of North America, close to the mount of Columbia river). The results of the study of physicochemical and biological processes, which control radioactivity, are interesting. It is found that the accumulation of iron in suspended matter in oceans leads to the transformation of a number of radio nuclides (Y91, Ce144, Nb95) in the suspended fraction. In the presence of iron the coefficient of accumulation of these isotopes by plankton increases by an order of magnitude. This shows that the disposal of radioactive wastes into oceans presents a definite hazard and can not be recommended (however, Japan, for example, does not adhere to this practice) [8]. It is obvious that no branch of industry has such a control and measures of protection against the pos- sibility of contamination of the environment as the nuclear power industry. A careful control of exposure of the population to radiation, the study of contamination of the environ- ment, and the measures of protection of the population are discussed in [8, 10, 12, 13] and other papers. It is shown in [13, 14] that detailed investigations of the contamination of the environment are carried out around APP: investigations of agricultural vegetations, drinking water, precipitations, water organisms, and fishes, domestic and wild animals, and so forth. The problems of utilization of ground, the settlement density, meteorology, geology, seismology, hydrography, hydrology of the region are also studied. It is especially important to know what is the admissible limit of dilution of water and air basins near APP by liquid and gaseous wastes. These investigations are necessary for the prognosis of possible contamination of environment at present and in future. The construction of APP almost excludes the possibility of ejection of fission products into the en- vironment during their normal operation. Only the gaseous isotopes Ar41, Xel", Kr85, H [1] and very 309 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 insignificant amount of 1131 can get into the atmosphere. Gaseous ejections of C14 and 1129 (latter with To = 1.7 ? 107 yr is formed during the processing of nuclear fuel) are described in [13]. Liquid disposals con- tain H3 and in very small quantities also Mn54, Co", Co", Sr", Sr", Ru106, Sb125, Cs134, Cs137, Ba140 [1, 13] The number and amount of ejections varies in wide limits during the operation of reactors. The average amount of liquid waste in reactors in USA and England in 1966-1969 was 6-11 Ci/yr (maximum up to 27 Ci /yr), tritium up to 3700 Ci /yr, noble gases up to 3.8. 105 Ci/yr (mainly Ar41 up to 2- 105 Ci/yr), which comprises about 24-28% of the admissible level for liquid wastes and 15% for gaseous wastes [1]. The largest yield of noble gases is observed in the operation of boiling water reactors (BWR) and in gas cooled reactors (GCR); the smallest yield is observed in reactors cooled by pressurized water (PWR). The pattern is reversed for the yield of tritium in the operation of these reactors. Thus the ejections from the American BWR in 1968 comprised [13] 240 thousand Ci/yr, of which Xe133 was 9000 Ci,Kr85 3 Ci, H3, 0.2 Ci, and11310.02 Ci.The annual liquid disposal was 2 Ci H3, 0.6 CiCo", and 0.9 Ci Co". Gaseous ejections of the American PWR during the year was 14 Ci H3, 3 Ci Kr"; the total gaseous ejection comprised 103-104 Ci, while the liquid disposals were estimated at 1000 Ci H3. The fuel treatment plants discharge Kr" in appreciable quantities. In liquid discharges Ru106, ura- nium, plutonium, americium, and curium have been detected [13]. The concentrations of radio nuclides in liquid discharges comprise 1.4. 10-10-2.2 ? 10-6 mCi/cm3. The ejection of noble gases into the atmosphere by Canadian reactors comprises an average of 6400 Ci/day from the first reactors and up to 440 Ci/day from the new reactors; the ejection of tritium is up to 30 Ci/day (ejection of 1131 is in all 10-5-10-3 Ci /day and about 10-2 Ci/day in the oldest reactor. The amount of tritium in liquid discharges goes up to 15 Ci/clay. In old reactors the ejection of Sr90 (up to 7.5 mCi/day) is observed; Cs134, Cs132, and Co" (6 ? 10-6mCi/cm3onthe average) are also present. At the beginning of 1971 the gas ejection at four APP of Japan comprised 8-10-4-11 mCi/sec (up to 1000 Ci/day. At "Mishana" APP the ejections in February 1971 comprised 0.1 Ci/day. Liquid discharges were up to 7-1200 mCi /month [81. Such ejections lead only to an insignificant concentration of radio nuclides in the environment. Thus the concentrations in expendable surface waters of some APP in the USA reached 100-270 nCi/liter, , 2-6 nCill3/m1 in drinking water, up to0.6 nCi Co"/ g in fish, up to 120 nCi Mn54/g in precipitations, and up to 57 nCi Co" /ml in vegetables [13]. A concentration of 1 nCi Co60/g was observed in the organisms of sea shells in the vicinity of one Japanese APP [8]. From the ejections mentioned above the population living in the immediate vicinity of an APP can re- ceive only a small dose of radiation. Thus the maximum doses of external radiation from ejections (mainly Ar41) from the tubes of Canadian APP in 1968 was up to 0.26 rem/yr at a distance of 1 km, and 0.037 rem /yr at 4.8 km. The total integral dose of radiation of the entire population at a distance up to 50 km is 16 man ? rem/yr [14]. Ata Japanese APP the dose at a distance of 1.5 km for constant wind and gaseous ejec- tion of 7500 mCi/yr is 7 mrem/yr [8]. In 1968 at an Americal BWR the dose of external radiation at a distance of 2 km was 10 mrem/yr; the maximum dose of internal radiation received by fishes in the region of fuel treatment plants was 4 mrem/yr [13]. Specialists of different countries use the standards recommended by the International Commission on protection from radioactivity (ICRP) in the design and construction of APP. However, there is a system of licensing and additional requirements in the zone of construction of APP. They amount, for example, [9], to the following: for the atomic industry in FRG a genetic dose of 2 ber in 30 years (instead of 5 ber accord- ing to ICRP) is acceptable. For long-range planning the dose from gaseous ejections for the population is restricted to 1 rem in 30 years or 30 mrem/yr. It is assumed that for different persons the dose must be approximately the same. At new plants charcoal filters and delay lines for gaseous ejections are used for purification. For liquid wastes also (in future planning) the acceptable dose is 1 rem in 30 years, uniformly distributed among the external radiation, internal radiation in drinking water, and internal radiation in cereal requirements. 310 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Individual enterprises are allowed an ejection of liquid wastes not exceeding 5-20 Ci/yr (without con- sidering tritium). The concentrations of radio nuclides in river water must not exceed 10-30 nCi /liter, and 3000 nCi /liter of triti urn (from all the sources excluding global fall-outs) . Drainage water with concentration larger than 5 ? 10 -4 MCi /Ml must be cleaned before disposal [9] . In Canada it is stipulated that an additional conditions that the genetic dose be no more than 104 man ? rem/yr, must be fulfilled for each reactor [14]. The concen- tration of radioactivity in water, discharged into oceans, must be below 10-7 ?Ci/cm3 [8]. In some papers a desire is expressed that radioactive discharges from APP be as low as practically possible [8, 15]. In [14] it is estimated that, if the ejections from APP cause 20% of the ICRP admissible dose, then 3.4 ? 104 man ? rem is received per million of population, or the maximum dose is 4.5-104 man ? rem per 2000 MW of electrical power per year taking into consideration the growth of power production in future. The radiation doses of the entire world population from the radioactive products`of APP up to the year 2000 are estimated in [1, 16]. It is calculated that by 2000 up to 500 MCi of tritium will go into the environment per year (from which the dose for each man will be up to 0.04 mrem/yr); the corresponding input of 1123 will be 6.3 .104 Ci (radia- tion dose for one man 0.2 mrem/yr) and of Kr85 7 ? 103 MCi (dose 0.4 mrem/yr)at a level of power production of 4260 GW/yr [1]. Thus, at present the radiation doses from radioactive materials produced in the process of peaceful uses of atomic energy are small and appreciably below the admissible levels recommended by international organizations. However, a sharp increase in the power generation from nuclear sources (almost by a factor of 200) by the year 2000 forces one to consider carefully the possibilities of contamination of the environment. Ac- cording to some estimates the doses on global scale may comprise about 1% of the values of the natural background, which is smaller than its variations. Different conditions over the globe, permeation of iso- topes and their passage along biological chains may change the results of these estimates by a factor of ten or more. This makes it necessary to watch the contamination of natural media carefully. A comparative estimate of the consequences of operation of ordinary power plants and APP, presented in a Soviet paper [16], is interesting. It is calculated that in the operation of ordinary enterprises even by the year 2000, for the dilution of toxic substances to the admissible level several thousand times larger amount of air is needed than in the operation of APP. The computations were done for large areas: for short-lived substances (or rapidly washed out from the troposphere) up to 107 1cm7, for long-life isotopes (Kr85 and H3) ? for the entire surface of the earth. The possibilities of accidents in APP (up to five cases in a year over the globe) were also taken into consideration. For ordinary electric power plants the calcu- lations were done for ,sulfur anhydride, ash, and other toxic substances. Furthermore, it was necessary to consider that the total amount of dissipated heat (which may, in the final analysis, cause undesirable climatic changes) per unit usable power of APP is appreciably less than in the operation of ordinary power plants due to the high efficiency. The use of atomic energy does not involve consumption of oxygen and does not lead to continuous increase of carbon dioxide in air. It is true that the amount of heat given off to water in the operation of APP is about 1.5 times larger than in the operation of ordinary power plants (per unit power) [15], which must be taken into consideration. This may cause undesirable heat contamination of water. An American paper [17] was devoted to the thermal effects accompanying the operation of APP. The growing reaction of the population and the society to the development of nuclear power was noted at the Geneva conference. This problem undoubtedly requires the most careful attention and painstaking analysis. A meeting of experts on the ecological aspects and public recognition of atomic energy was held during the conference. The representatives of the USSR, India, Spain, Italy, Great Britain, USA, France, Czec- hoslovakia, Switzerland, Japan, and Argentina participated in the meeting. The experts produced a sum- marized report of the conclusions in short statements (4-5 min) given by each of them on different problems. The general problems of the effect of APP on the environment were discussed and APP and plants operating with chemical fuel (the representative of the USSR reported on this) were compared; possible ejections from APP into the environment, the problems of safety of the society, and also the possible ways of entrance of isotopes into human organism, the safety standards, thermal effects of APP, possible accident situations in atomic power plants, the reaction of the society to the use of atomic energy in daily life were discussed. 311 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Problems regarding the role of the scientist in the formation of correct public opinion at the epoch of development of nuclear energetics, the fate of accumulating radioactive wastes, the basis of the existing standards for ensuring safety, lowering of these standards, the possibilities of bringing a correspondence between the obtained electrical power and the dose, etc were also touched upon. The conference stressed that the task of the scientists consists in a careful investigation of the con- tamination of the environment and an accurate prognosis of the contaminants considering all possible situa- tions. The -role of the nuclear energetics in reducing the contamination of the environment by toxic sub- stances from ordinary fuel was noted. Thus, the development of nuclear energetics can ensure the conservation of adequately clean environ- ment; the replacement of the energy produced from common fuel by atomic energy results in a decrease of the contamination of the environment by toxic substances formed in the combustion of ordinary fuel. LITERATURE CITED 1. IV Geneva Conference (1971), Paper No. 652 (Voz). 2. Environmental Contamination by Radioactive Materials, Proc. of a Seminar, Vienna (1969). 3. Environmental Aspects of Nuclear Power Stations, Proc. of a Symposium, New York (1970). 4. E. A. Fedorov et al., See [1], paper No. 686 (USSR). 5. F. A. Tikhomirov et al., See [1], Paper No. 685 (USSR). 6. S. Auerbach et al., See [1], Paper No. 085 (USA). 7. P. Kamath, See [1], Paper No. 536 (India). 8. T. Masatoshi et al., See [1], Paper No. 253 (Japan). 9. K. Aurand et al., See [1], Paper No. 399 (France). 10. E. Kunz et al., See [1], Paper No. 550 (Czechoslovakia). 11. V. M. Vdovenko et al., See [1], Paper No. 457 (USSR). 12. A. I. Burnazyan et al., See [1], Paper No. 429 (USSR). 13. B. Kahn et al., See [1], Paper No. 087 (USA). 14. A. Marko et al., See [1], Paper No. 160 (Canada). 15. E. Larson Clarence et al., See [1], Paper No. 723 (USA). 16. Yu. A. Izrael and E. N. Teverovskii, See [1], Paper No. 684 (USSR). 17. R. Foster, See [1], Paper No. 086 (USA). 312 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 BOOK REVIEWS NEW BOOKS Modelirovanie i Optimizatsiya v Avtomatizirovannykh Sistemakh Upravleniya. [Simulation and optimi- zation in automated control systems], G. N. Balasanov, Atomizdat, Moscow (1972). The book outlines the basic methods of optimum process control based on computerization (linear and dynamic programming, game theory and Monte Carlo techniques, operations research and queuing theory, pattern recognition, theory of learning and adaptive systems, theory of optimum systems). The requisite mathematical concepts are discussed. The bulk of the examples cited refer to optimum control, and to mathematical description of technolo- gical processes in hydrometallurgy and in chemistry. The methods described in the book are likewise ap- plicable in the chemical, petroleum and petrochemical, metallurgical, and other diverse branches of in- dustry. The book is intended for students in technical colleges, for graduate students, and also for research workers in planning institutes and industrial plants interested in production control problems. Rukovodstvo po Vychisleniyu i Obrabotke Rezulitatov Kolichestvennogo Analiza. [Handbook on com- putation and processing of quantitative analysis data], R. I. Alekseev and Yu. P. Korovin, Atomizdat, Moscow (1972). The book discusses the basic problems that workers in analytical laboratories have to confront in the computation and statistical processing of the results of quantitative analysis of the composition of a sub- stance. The methods for computing and processing the analysis results are presented in "cookbook recipe" format, with numerical examples, so that the techniques recommended can be utilized directly by analyti- cal chemists regardless of their background, or lack of one, in mathematical statistics. The book is written for analytical chemists working in all branches of the national economy. Radiatsionnaya Biokhimiya Timusa. [Radiation biology of the thymus], E. F. Romantsev, V. D. Blokhina, Z. I. Zhulanova, N. N. Kashchinko, and I. V. Filippovich, Atomizdat, Moscow (1972). The book presents modern concepts on the physical and biochemical mechanisms operative in exposure of the thymus, one of the most highly radiosensitive tissues found in the mammalian organism, to ionizing radiations. This lymphoidal tissue is involved in immunological reactions which are of general biological significance. The book goes into the mechanisms at work when the thymus is affected by ionizing radiations and by antiradiation protectants. Information on the structure and function of the thymus is cited; distur- bances in nucleic acid and protein metabolism and in the oxidative phosphorylation process in the thymus in response to radiation exposure are described, as well as the way these processes are affected by the presence of chemical radioprotectants. The book is written for specialists in various lines of work interested in current problems in radio- biology and radiation medicine, for health physicists and medical radiologists, and for senior biology ma- jors in universities and medical institutes. Svoistva Deformirovannykh Yader s K = 1/2. [Properties of deformed K = 1/2 nuclei], B. S. Dzhele- pov, G. F. Dranitsyna, and V. M. Mikhailov, Nauka, Leningrad (1972). The most frequently encountered deformed atomic nuclei are those whose ground states or excited states have the quantum number K = 1/2. Several interesting features arise in the structure of the rotational Translated from Atomnaya Energiya, Vol. 32, No. 4, pp. 278, 286, 292, April, 1972. ? 1972 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. 313 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 bands, in the intensity ratios of the transitions, in the magnetic moments, etc., some to light. The mono- graph reviews all of the available experimental material on the range of nuclides 150 < A < 190 and the range A > 230, and discusses predictions of theory and inferences that can be drawn from the experimental data. A generalized model and the results of a microscopic approach to the description of the properties of deformed nuclei are utilized in the theoretical analysis. The book is written for scientific-research workers and for graduate students working on the structure of the nucleus. Beta-Protsessy. Funktsii dlya Analiza Beta-Spektrov i Elektronnogo Zakhvata. [Beta-decay pro- cesses. Functions for analysis of ,3-ray spectra and electron capture], B. S. Dzhelepov, L. N. Zyryanova, and Yu. P. Suslov, Nauka, Leningrad (1972). This book is devoted to the functions required for analysis and processing of experimental data on nuclear )3-decay and capture of orbital electrons. The self-consistent potential of the atom is utilized in the calculations, and the finite dimensions of the nucleus are taken into account at the same time. The tabular data presented in the book make it possible to analyze the shape of allowed and forbidden /3-ray spectra, to determine the value of the product ft, to find the relative probability of capture of electrons from different shells and subshells of the atom. The book is written for experimental physicists and theoretical physicists working with spectroscopy of the atomic nucleus, and may also prove useful to graduate students specializing in nuclear physics. Neitron-Neitronnyi i Neitronnyi y-Metody v Rudnoi Geofizike. [Neutron?neutron and neutron ? y logging techniques in mining geophysics], E. M. Filippov, B. S. Vakhtin, and A. V. Novoselov, Nauka, Novosibirsk (1972). The book presents general information on neutrons, on neutron sources and neutron detectors, on safety techniques, and provides a classification of relevant techniques, etc. Separate sections of the book deal with laboratory, mine, and borehole modifications of those methods. Extensive material available on these topics is reviewed and generalized systematically. Emphasis is placed on work done by the authors in recent years. The book will be of interest to staff members of scientific-research institutions, and to workers on the staff of production planning organizations interested in applying nuclear physics techniques or interested in learning about the potentialities of those methods. Fiziko-Khimiya Redkikh Metallov. [Physical chemistry of rare metals], Nauka, Moscow (1972). This collection of articles is devoted to the 60th birthday of the major Soviet metals scientist E. M. Savitskii, Corresponding Member of the USSR Academy of Sciences, Disciples and colleagues of the scientist generalize the results of their research in a series of articles and acquaint the reader with the latest achieve- ments in the fields of the production technology of ultrahigh-purity single crystals of rhenium, vanadium, tantalum, yttrium, scandium, gadolinium, ruthenium, and rhodium; production of pure metals and of alloys of tungsten, molybdenum, niobium, etc. Results of the construction of over a hundred "composition vs. property" phase diagrams for those materials are demonstrated. Results of determinations of new chemi- cal compounds and of calculations of the Fermi surface, in order to ascertain the interrelation between the structure and properties of the substances studied, are cited. This publication is written for a broad range of research personnel; metals scientists, metallurgists, machine designers and instrument designers engaged in the study, winning, processing, and utilization of refractory metals and rare metals in industry, and also for students and instructors in chemical, metallur- gical, and machinery design colleges. Svobodnoradikal'noe Sostoyanie v Khimii. [The free-radical state in chemistry], Nauka, Novosibirsk (1972). This collection includes articles by leading Soviet scientists and foreign scientists devoted to the most urgent topics in the physics and chemistry of free radicals. The vigorous development of this new branch of chemical physics has made it possible to present convincing and unambiguous proof of the decisive role played by free-radical processes in various radiation-chemical and photochemical reactions, in combustion processes, and so forth. The collection of articles is dedicated to the memory of Academician V. V. Voe- vodskii, whose work and activities played a decisive role in the development of various research trends 314 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 in the physics and chemistry of free radicals. Some of the articles were written by disciples of V. V. Voevodskii. The book is written for a broad readership of research workers engaged in various branches of physi- cal chemistry, and also for chemists, biologists, and physicists interested in the physics and chemistry of free radicals. Metallotermicheskie Metody Polucheniya Soedinenii i Splavov. [Metallothermic techniques in the pro- duction of compounds and alloys], Nauka, Novosibirsk (1972). Metallothermic methods for the production of intermetallic compounds and alloys prove to be more convenient, technologically and economically, than methods based on direct fusion of the components, in many instances of practical interest. This collection of articles reports the results and research findings on metallothermic synthesis of intermetallic compounds and alloys in the reduction of oxides, halides, and other substances. The optimum conditions for producing the compounds and alloys are ascertained, as well as the physicochemical characteristics of the substances involved in the reactions; in some instances, at- tempts are made to lay bare the underlying mechanism and the kinetics of the reduction process. The book is written for theoretical chemists and for practising chemists. Elektricheskoe Modelirovanie Yavlenii Teplo- i Massoperenosa. [Electrical simulation of heat-trans- fer and mass-transfer phenomena], L. A. Kozdoba, Energiya, Moscow (1972). This book deals with research on the heat-transfer conditions affecting machine parts, assemblies, facilities, and rooms based on the use of such electrical simulators as resistor networks and combined electrical simulating models. A procedure is presented for electrical simulation of linear and nonlinear problems in nonstationary heat transfer and nonstationary mass transfer. Examples of solutions obtained with electrical simulators are given for direct as well as inverse and inductive problems in heat condition. The book is intended for engineers and research scientists, and may prove useful to technical college students. Uspekhi Fiziki Plazmy. Tom 1. Fizika Vysokotemperaturnoi Plazmy. [Translation of: Advances in Plasma Physics. Vol. I. Physics of High-Temperature Plasma, edited by A. Simon and W. Thompson, New York (1968)], Mir, Moscow (1972). A team of leading American specialists on plasma physics (Dyson, Furth, Kroll, Fowler) decided to undertake a complete review of the advances achieved in plasma physics and applications of plasma physics in various fields. The book includes part of the material appearing in the first volume of the original Ameri- can edition. Its contents cover a range of key problems in the physics of a high-temperature plasma re- lated to emission, confinement, stability, and thermodynamics of an unstable plasma. The contents reflect the current point of view on those topics, embodying generalizations of the contents of numercus papers published up to 1968 only in the periodical literature. The book is of considerable interest both to specialists in plasma physics and to research scientists and technicians concerned with the topics discussed, and also to senior undergraduates majoring in related branches of physics. Magnitnye Poluprovodniki. [Magnetic Semiconductors, S. Methfessel and D. Mattis, translated from the English original in: Handbuch der Physik, Bd. 18/1], Mir, Moscow (1972). This is the first review to appear in the worldwide literature on the physics of magnetic semicon- ductors, and sheds light on several topics of theoretical or experimental interest. The quantum mechanism underlying the magnetic and electrical properties of magnetic semiconductor materials is discussed, and a wealth of experimental data is presented. The book will be useful to research physicists and engineers engaged in theoretical and experimental studies of the properties and applications of magnetic materials, and also to readers interested in the phys- ics of semiconductors, as well as to senior undergraduate students and graduate students in physics and en- gineering physics technical colleges majoring in solid state physics. Garmonicheskii Ostsillyator v Sovremennoi Fiziki: ot Atomov do Kvarkov. [Translation of: The Har- monic Oscillator in Modern Physics from Atoms to Quarks, New York (1969)], M. Moshinsky, Mir, Mos- cow (1972). 315 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 M. Moshinskii, a professor at the University of Mexico, is a recognized authority in the field of ap- plications of group-theoretical methods to quantum mechanics. The book, which is based on a lecture course given by this author, is a unique monograph in which a single model is utilized in the investigation of some crucial problems in theoretical physics. Some common vantage points are used to attack what appear to be entirely dissimilar systems (molecules, atoms, molecules). The book is written in a clear and lucid style, so that it is accessible and interesting not only to specialists but also to student physics majors. Metod Fazovykh Fu_nktsii v Teorii Potentsionaltnogo Rasseyaniya. [Translation of: Variable Phase Approach to Potential Scattering], F. Calogero, Mir, Moscow (1972). F. Calogero is one of the founders of a new and efficacious method for solving problems in quantum mechanics, the method of phase functions. This method, developed in the past 10-15 years, enables scien- tists to obtain many general results in quantum mechanics in a simple manner. The method is particularly effective in dealing with scattering problems, and also in computer work. Since this method has not yet filtered down to standard courses given on quantum mechanics, the book will be useful to students specializing in the field of theoretical physics, and to instructors as well. It is also needed by theoretical specialists, since the literature on this topic in the Russian language is meager. Osnovy Kvantovoi Elektroniki. [Translation of: Fundamentals of Quantum Electronics, New York (1969)], R. Pantell and H. Puthoff, Mir, Moscow (1972). This is a monograph textbook on the fundamentals of quantum electronics. The book expounds a uni- que approach to many of the relevant problems, including the latest achievements in the fields of nonlinear optics, semiconductor lasers, and interaction of radiation with matter. The textbook contains problems and exercises. The book is written for senior undergraduates majoring in engineering physics, radio physics, and electronics, and also for specialists in related areas who are interested in familiarizing themselves with the fundamentals of quantum electronics. Kataliticheskie Prevrashcheniya Uglevodorodov. [Translation of: Catalytic Conversion of Hydrocar- bons, London (1969)], J. Germain, Mir, Moscow (1972). The book discusses conversions of hydrocarbons belonging to different classes to heterogeneous cata- lysts, and specifically discusses the oxidation of hydrocarbons, one of the most prominent processes in modern photochemistry. Classification of catalysts (inorganic complexes, metals, acidic homogeneous and heterogeneous catalysts, bifunctional catalysts) is presented, with analysis of the operating mechanisms of the catalysts from the standpoint of modern concepts of physical chemistry and organic chemistry. The book is of interest to physical chemists, organic chemists, and petroleum chemists working in research institutes and in industrial plants. Technika Radiacyjna. Podrecznik Akademicki. [Radiation engineering Academic textbook], Wydaw- nictwa Naukowo-Techniczne, Warszawa (1971) [in Polish]. This text covers ionizing radiations used in radiation engineering, and describes isotope sources and electrical sources of ionizing radiation, industrial radiation facilities, dosimetry, radiation polymerization and irradiation of polymers, radiation conservation of foodstuffs, the use of radiation techniques in chemical process technology, and also radiation effects in inorganic solids. The book is intended for students majoring in chemistry in technical colleges. Fizyka dla Inzynierow. Fizyka Wspolczesna. Czesc 2. [Physics for engineers. Modern Physics. Part 2], Wydawnictwa Naukowo-Techniczne, Warszawa (1971) [in Polish]. The book presents general information on atomic physics, solid state physics, and nuclear physics. The material is presented in concise format, and is richly illustrated. The book is intended for engineers of various specialities, and also for students enrolled in technical colleges. 316 Declassified and Approved For Release 2013/03/01: CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 ANTIMONY, BISMUTH, ARSENIC, AND OTHER ELEMENTS IN ORE BODIES AND HALOES OF A URANIUM ? MOLYBDENUM DEPOSIT G. I. Rossman, N. A. Stepanova, UDC 550.8 I. V. Sychev, and G. A. Tarkhanova A geochemical assessment of radiometric anomalies of a uranium mineralization involves determina- tion of the group of indicator elements of this mineralization within the anomalies. Lead and molybdenum are typical indicator elements of many uranium deposits; the sensitivity of their determination by standard analytical methods is fairly high [1]. However, in regions containing lead and molybdenum mineralizations as well as a uranium mineralization, the use of only lead and molybdenum for assessing radiometric anom- alies may lead to errors. In such cases one must use other indicator elements of uranium mineralization, such as arsenic, bismuth, antimony, and thallium. However, as the sensitivity of determination of these metals by standard methods is usually inadequate, their value as a criterion for prospecting has never been recognized. Our paper gives the results of an investigation of the distribution of arsenic, antimony, bismuth, tin, mercury, and thallium in ores and country rocks of a typical uranium-molybdenum deposit. With the ex- ception of mercury, these elements were determined by highly sensitive chemical and chemical- spectral analysis methods [1-5]; mercury was determined by the atomic absorption method. The sensitivity of these analytical methods is sufficiently high and the errors fairly small (Table 1), which enables one to detect and trace the distribution of the elements in ores and the country rocks. The threshold sensitivity of the analytical methods for arsenic, antimony, bismuth, tin, mercury, and thallium is one order of magnitude higher than that of simple spectral analysis by the "spill" method. The ore bodies of this uranium-molybdenum deposit are localized in a band of alternating volcanic and sedimentary rocks, in acid tuffs, and occur in blocks bounded by disjunctive dislocations (Fig. 1). These ore bodies, lying in different structural blocks, have been oxidized and leached to different degrees. Samples were taken from borehole cores and the walls of underground mine workings by the procedure in [1, 61; replicas of trench samples were investigated within the limits of the ore bodies. TABLE 1. Sensitivity of the Analytical Methods Element Mean content of elements in acid rocks, wt. 0/, Threshold sensitivity, wt , Accuracy of determina- tion, rel. 07, Threshold of sensitivity in local geochemical backgrounds according to A. P. Vinogradov (1962) local geochemi- cal background (1969) spectral analysis highly sensitive method spectral analysis highly sensitive method spectral analysis highly sensitive method As Sb Ti Bi Hg Sn 1.5.10-i 2.6-10-5 1-10-6 3-10-4 8-10-6 1.5-10-4 4-10-4 2 - 10-4 1-10-5 8-10-4 5-10-6 2-10-5 3-10-3 5.1O-4 5-10-5 1-10-5 1-10-2 1'10-5 1-10-4 1-10-4 1-10-5 2-10-5 1'10-7 1.10-5 120 80 80 85 200 120 20 32 30 33 50 33 7.5 2.5 50 1.25 2-106 100 0.25 0.50 1.0 0.025 2 0.5 Translated from Atomnaya Energiya, Vol. 32, No. 4, pp. 279-285, April, 1972. Original article submitted May 6, 1971. 03 1972 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. 317 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 zA, 318 g. 0 Cl) 0 ....... q-1 . 4-1 Cq 0 in 0 ,....i 0 in +' C17 0 0 CD CI) 0 c; C). 75 N 0 ''''' 0 "--? V r-I ^- N 1 o .. ;; cl -4, 0 ;/).? P 0 0 Cll a) CD? - Cll F-1 bp 0 ''''-' r?-i fa, --- 0 r-I o? E g a) cii 71> d ''''' g 1 ? o cc) Cil N 4-A 0 ....Y 0 Ci) 0 C.) 0 :14 C5 0 .1-1 r0 ????? (1) 0 0 4.1 "4 0 0 ;4' O cC'Ti ..-1 Cri a. ... P A 0 4.4 C.) ,--' Cr'... 0? 0 at cri 0 0 0 MI (1) O) $.4 g no ? Q.) 0 X) 0 0 ..0' E CD C.) at 0 03 rtj E P X 0 0 GO Ci) 4-4 0 0 CD (:) 4-1 0 CG N 0 CI) o co CD CV >1 C' E f., TS c= w 0 C: ,c1) 0 4 0 ?,-. ?-o .a)_-'1- 0 L..-- 0 CD ...-)ril CD ,17. P ..,?5., 9c; g 0 4-I A ..1.. r..4 0 0 0 0 Cj C9 04-4 [E ?,--, ,g? 0 -4.- +4 0 o 0 co., U) N I U) In C.) i C3F-I C:'?. Lt C?;\)c 1 r-I G.) ?s' A-, ..-4 Li.4. 0 .1:2 ._1,) CD > c; ?CG A g E I ?1-1 0 r-I CD 4 ?,-, Declassified and Approved For Release 2013/03/01: CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Ores r = - 1 r = +1 U-Mog U-Snx U-TLx U-Cur U- 8ix (J-Asx ti-Cu (I-As U-Pb U-Sb r = Ores r=+1 Cu-Cux Cu-As* Si-Ask Cux-Asx Sbx-Bix Pb - Cux Ho-As Pb-Sb MO-Cu Ho- Pb Pb- Cu MO -Snx Cu -Se As -Snx Cd-Sn' r=- U-Snx Haloes of country rocks r=+1 U-Sbx U-Cul U-811 U-Asx U-Cux (1-As U-Pb r = Fig. 2. Pairwise correlations of elements in the ore bodies and haloes: x denotes ele- ments determined by the highly sensitive method; r denotes the correlations. It was established that simultaneously with uranium, molybdenum, lead, and copper, arsenic (more than 100), antimony (more than 10), bismuth (about 100), mercury (about 80), and thallium (about 100) are concentrated in the ores of the deposit.* However, the ores have low tin contents (0.1). The data (Fig. 2, Table 2) clearly indicate a close relation between these elements (with the exception of tin) and molybdenum and uranium (their minerals and the minerals present in paragenesis with them). Antimony, arsenic, and bismuth are not only concentrated as admixtures, but form their own minerals, of which the most typical is fahlerz. A much smaller part of the arsenic is also combined with arsenopyrite. Mercury is concentrated as an admixture in fahlerz and is found as occasional segregations of cinnabar. A considerable amount of these elements is present in collomorphic pyrite as an admixture. These minerals were segregated at about the same time as uraninite. Hence it follows that the bulk of the antimony, arsenic, bismuth, thallium, and mercury is related to the productive stage of the ore-form- ing process. These elements may be regarded as mineralization indicators which form aggregation haloes; this is confirmed by the data of Fig. 2. On the other hand, tin forms an evacuation (negative) halo. Haloes of indicator elements are contained mainly in the beds of tuffs adjoining the ores; they are larger than the uranium haloes above the site where the ore bodies taper out (the boundary of the haloes is drawn along the lower anomalous values of the element concentrations, which differ markedly from their background concentrations at a unilateral significance level of 0.05). Haloes of thallium and mercury are also observed around the ore bodies, but their effective dimen- sions have not been established. Judging from the existing data, ?the mercury halo reaches beyond the limits of the bed adjoining the ore and is larger than the uranium, antimony, bismuth, arsenic, molybdenum, lead, and copper haloes. The thallium halo is apparently comparable in size with the bismuth halo. *The figures in parentheses are the concentration coefficients with respect to the local geochemical back- ground. 319 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 TABLE 2. Form of Occurrence of Uranium in Indicator Elements in Ores, the Surround- ing Geochemical Haloes, and the Unaltered Rocks Indica- tor ? ele- ment In ores In haloes In zone of oxidation and leach- ing (halo) In unaltered rocks A B A B A B A B U Uraninite Sooty uraninite Secondary ura- nium min- erals ? Sooty ura- ninite ? Sooty ura- ninite Secondary uranium minerals (silicates, arsenates, phosphates) Manganese hydro- xides Gypsum Kaolinite _ Orthite Monazite Zircon Mo Femolite Molybdenite Molybdenum black Uraninite Skolite Calcite Hematite Molybdenum black Calcite Chlorite Powellite Wulfenite In all secondary ? uranium mineralst Manganese and iron hydroxides Kaolinite Pyrite Ti ? Femolite Pyrite Marcasite ? Pyrite Iron hydroxides Manganese hydro- xides ? As Arsenopyrite (a little) Fahlerz (a little) Chalcopyrit ? Skolite I CarbonateIof Quartz I Pyrite ? Uranospinite Torbenite _ In all secondary uranium miner- ala (a little in uranium silicates Powellite Malachite Pyrite In minerals the ? electro - magnetic fractions Sb Fahlerz Uraninite Hematite Pyrite Femolite ? # Urani.um?molyb- _ denum black Torbenite Malachite Manganese hydroxides Pyrite Hg Cinnabar Fahlerz ? D ? ? ? Bi Fahlerz Uraninite Hematite Tennantite Early pyrite Tennantite Hematite Sooty urani- nite ? Secondary urani- ? um phosphates Malachite In minerals of the electro - magnetic fractions Note: A) Intrinsic mineral forms; B) as admixtures in the minerals; the principal form of the minerals is shown in boldface. An asterisk denotes uranium in sorbed form; a dagger denotes an admixture of molybdenum, characteris- tic of secondary uranium minerals of U?Mo ore bodies; a question mark denotes that the forms of occurrence have not been revealed. A characteristic feature of these haloes is the zonality of the structure,* which is expressed in a regular variation of the dimensions of the haloes, the correlation coefficients of the indicator elements, their mean contents, and the linear productivities characterizing the different hypsometric levels, which replace one another to the dip of the ore-adjoining structure. The most objective expression of the zonal distribution of the elements is given by the values of the linear productivities (Fig. 3, Table 3). *It is not our intention to examine the nature of this zonality. A study of this very complex problem is the subject of special investigations of the diitribution of a radiogenic admixture of Pb2" and uranium in cross section of ore bodies and the surrounding haloes. According to the data of our comparative investigations on isolated ore bodies of deposits with different degrees of oxidation, the primary zonal distribution of the elements developed above the sites where the ore bodies taper out is very similar to that in the zones of oxidation and leaching of ore bodies of similar primary composition [7]. 320 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 TABLE 3. Change in Values of Linear Productivities of Haloes of Uranium, Its Com- panion Elements, and Their Ratios Bore_ tole 'the No. Depth to dip of the structure Linear productivities. Mo b Ra.tios of linear producti- vities Geological position of sarnpling site U As Sb Bi Sn As/U Sb/U Bi/U Sn/U 2675 60 0,0375 0,0665 0,035 0,00290 0,0142 8,9 4,7 0,38 1,9 Surface beaching zone 2632 80 0,0117 0,0382 0,028 0,0006 0,0167 3,27 2,4 0,054 1,43 2656 140 0,0247 0,0393 0,0163 0,0004 0,0065 1,59 0,66 0,016 0,26 Zane of leaching and oxi- dation of primary ores (upper parts of the ore bodies) 2578 160 0,0240 0,0296 0,0150 0,0010 0,0078 1,23 0,63 0,044 0,32 2634 180 0,0247 0,0355 0,0147 0,00062 0,0061 1,44 0,59 0,025 0,25 2533 320 0,0624 0,0236 0,0221 0,00091 0,0053 0,38 0,35 0,015 0,1 Zone of ore body with oc- currence of regeneration processes (lower parts of the ore body) 2488 340 0,0103 0,0272 0,0146 0,00022 0,0109 2,64 1,46 0,022 1,0 2519 400 0,0027 0,0251 -- -- __ 9,3 __ __ Zone of development of haloes below the boundary of tapering out of the ore body 2517 420 0,0029 0,0079 0,0083 0,00051 0,0056 2,7 2,86 0,19 1,93 2625 460 0,0015 0,0224 0,0094 0,00106 0,0049 15,0 6,3 0,70 3,28 Zwie of influence of under- lying ore body 2622 465 0,0048 0,0155 0,0118 0,00119 0,0071 3,23 2,5 0,25 1,5 2620 480 0,0019 0,0248 0,0530 0,0037 0,0058 13,6 23 1,9 3,2 It will be seen from the data that prefential deposition of arsenic, antimony, and bismuth is corre- lated with the upper horizons of the haloes, located above the ore body. In contrast with this, the linear productivity of uranium in the haloes is maximal for the level of the middle and lower parts of the ore body. The tin content in the region of its "negative" halo is somewhat higher above the upper parts of the ore body. An analysis of the change in the linear productivity ratios As/U, Sb/U, Bi/U, Sn/U to the dip of the ore-adjoining bed reveals that these ratios regularly decrease as one approaches the ore body. The maxi- mal gradient corresponds to the As/U ratio. It should be noted that there is a slight change in the sign of the gradient of the values of the linear productivities As/U, Sb/U, Bi/U, and Sn/U in the haloes located below the tapering out of the ore body. Here we again observe an increase of the ratios of the linear productivities of arsenic, antimony, bismuth, and tin to uranium. Such a change in gradient indicates the presence of another, deep ore body, the upper parts of the haloes of which were superimposed on the lower parts of the haloes of the investigated ore body. In fact, a hitherto-unknown blind U - Mo (uraninite -hematite) ore body was discovered 100 m below the point at which the investigated ore body tapers out (see Fig. 1). The data enable us to infer that arsenic, antimony, and bismuth are accumulated in the zones of oxida- tion and leaching of the mineralization (see Fig. 3, Table 3). This is confirmed both by their absolute linear productivities and by the ratios of the productivities to those of uranium. Removal of uranium from the oxidation and leaching zones is proved by comparative investigations of lead isotopes and uranium contents [7]. The place of mercury and thallium in the scheme of zonal structure of the haloes has not been finally established. The existing data indicate that high concentrations of mercury and thallium are characteristic of the upper parts of the haloes developed above the ore bodies. Another characteristic feature is the 321 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 U n.10-4 As n.10-4 0 100 200 300 400 500 600 0 100 200 300 400 500 600 i1410 III ir 100 200 300 400 500 Sb n10" 0 100 200 300 400 11,?? 100 200 300 400 500 Fig. 3. and their n.10-4 100 200300 400 0i n.10-5 0 100 200 300 400 I I I ? 100?...............:_o__ 200' 300 300. 400 500 5,0 m 0 1 5 6 7 8 9 10 11 12 13 - 4 ,FL, 11 ->x . /4 / As a ? 1 3 % 300 400 500 ? :),,.?,-..&-0.,..,. . --xii.42-x 44 - U 1,5 Cn Bi GiEl 2 CI 3 Change in linear productivities of haloes of uranium, its companion elements (a) ratios (b) to the dip of the U-Mo ore body (see Table 3): 1) ore zone exhibiting oxidation and extraction processes; 2) ore zone exhibiting regeneration (cementation) pro- cesses; 3) intersection of the central part of the ore zone by the exploratory drill-holes. asymmetric structure of the haloes of these elements and their extensive occurrence in the strata above the ore body. Thus the ores and adjoining rocks of this U-Mo deposit, localized in volcanic rocks, contain anoma- lous concentrations of antimony, arsenic, thallium, and mercury. With respect to uranium, these elements are concentrated in haloes above the point at which the ore bodies taper out to the rise, and persist during weathering of the country rocks. LITERATURE CITED 1. 0. 0. Kablukov et al., Use of Dispersion Haloes of Uranium and Its Companion Elements in Prospect- ing for Hydrothermal Uranium Deposits. Handbook [in Russian], Nedra, Moscow (1964). 2. Symposium: Chemical Analysis of Mineral Raw Material [in Russian], No. 8, Nedra, Moscow (1965), p. 104. 3. Ibid., p. 165. 4. Symposium: Chemical Analysis of Mineral Raw Material [in Russian], No. 11, Nedra, Moscow (1968), p. 43. 5. N. A. Stepanova, L. I. Zemtsova, and T. A. Butkina, Papers of the Seminar "Determination of Microimpurities? [in Russian], Vol. 1, MDIPT im F. E. Dzerzhinskogo, Moscow (1968), p. 3. 6. D. A. Vigdorovich et al., Provisional Instructions for Geochemical Prospecting for Pyrites - Poly- metallic Deposits in the Presence of Very Thick Unconsolidated Deposits [in Russian], Seriya Obmena Opytom, No. 34, ONTI VITR (1960). 7. G. I. Rossman et al., Izv. Akad. Nauk SSSR, Seriya Geol., No. 1 (1971). 322 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 RADIATION-INDUCED GROWTH OF POLYCRYSTALLINE a-URANIUM M. A. Vorob'ev, V. F. Zelenskii, UDC 621.039.548.3 E. A. Reznichenko, and A. S. Davidenko Anisotropic growth of the components of polycrystalline a-uranium crystallites lies at the basis of radiation-induced growth of that uranium phase. Consequently, the problem of what mechanism underlies radiation-induced growth of polycrystalline uranium reduces to ferreting out the relationship between the growth of single-crystal uranium and the growth of polycrystalline uranium, while ignoring the effect of the grain boundaries and of the dislocation structure of the polycrystalline uranium on the growth rate. This problem arose earlier in calculations of what is termed the growth index, characterizing the de- pendence of radiation-induced growth of polycrystalline uranium on the degree of definition of the texture [100] or [010] (see references [1, 2]), and also in the discussion of the possible effect impurities might have on radiation-induced growth of uranium single crystals. The problem is that the investigation was carried out on polycrystalline specimens, and the results had to be extrapolated to the case of single crystals in order to reach definitive conclusions [3, 4]. Currently existing methods for calculating the growth index [1, 2] based on the assumed linear rela- tionship between texture and growth rate, fail to take into account interactions between the crystallites, so that they are not of much help in understanding the true relationship between the growth of single-crystal uranium and the growth of polycrystalline uranium. A plausible mechanism underlying radiation growth of polycrystalline uranium, with the interaction between variously oriented crystallites in the irradiated poly- crystal taken into account, has been put forth in [5]. It was shown that the interaction between crystallites constituting a polycrystalline aggregate and ex- posed to radiation is capable of bringing about changes in the initial orientation of the crystallites when adaptive plastic deformation of the crystallites takes place by twinning. It is proposed that this will sub- sequently bring about the same rate of deformation of all the crystallites in the direction of the overall ani- sotropy of the material, while at the same time determining the observable rate of radiation-induced growth of the polycrystal as a whole. The change in the initial orientation of the crystals is a necessary prere- quisite for radiation-induced growth of polycrystalline uranium, in conformity with such a twinning mecha- nism accompanying adaptive plastic deformation, and also as a consequence of it. It is not clear, however, just how radiation-induced growth of uranium must come about in the case where deformation by twinning is hampered, or is absent altogether, at elevated irradiation temperatures and at a low rate of deformation. For example, it has been pointed out [5] that only 10% of the adaptive plastic deformation takes place by twinning even at ?196?C, and that the bulk of the deformation occurring does so by gliding. Without completely ruling out the possibility of some reorientation of the crystals in response to irradiation, we can anticipate that this is not the sole cause of the common and identical rate of deformation of all the crystals in the direction of growth of the polycrystal. An alternative mechanism linking the radiation-induced growth of a-uranium single crystals and polycrystals is discussed in the pre- sent article. Mechanism Underlying Radiation-Induced Growth of Polycrystalline a-Uranium. We consider a poly- crystalline specimen of uranium exhibiting a certain degree of anisotropy. Under irradiation, the interac- tion between the growing crystals brings about a state of affairs where the crystals will deform, indepen- dently of their orientation, and at the same rate in the direction of the overall anisotropy of the specimen. Translated from Atomnaya Energiya, Vol. 32, No. 4, pp. 287-291, April, 1972. Original article submitted April 19, 1971. C 1972 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. 323 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Suppose that the external stresses have no effect on the radiation growth processes in the single crystal [5]. Then the rate of growth of the crystallites comprising the polycrystalline aggregate can be assumed equal to the rate of growth of a free single crystal for those irradiation conditions. The effective rate of radia- tion growth of the polycrystal in the direction of overall anisotropy will be determined by the relationship between the rate of radiation-induced growth of the crystals with preferred orientation and the rate of com- pensating plastic deformation. In order to determine the rate of the compensating plastic deformation, we consider those factors contributing to that deformation. Clearly, the deformation is brought about by re- straining stresses on the part of crystals with other than preferred orientation. These stresses can be determined from the condition (801+ (8p. d)i = (8 g)2 + (8p. d)2; where the subscript 1 refers to crystals with preferred orientation, the subscript 2 refers to the remainder of the crystals; g and ip.d are the rate of radiation-induced growth and the rate of plastic deformation, re- spectively; 01, G2 are the stresses generated in the interaction between crystals 1 and crystals 2; f is the ratio of the transverse cross section area of crystals 2 to the area of transverse cross sections of crystals 1. If the expression for the dependence of the rate of plastic deformation of crystals 1 and 2 on the stress is known, then we can find the effective rate of radiation-induced growth of the polycrystallite once we have determined 01 and 02. Irradiation is known to generate appreciable internal stresses in polycrystalline uranium through the interaction between crystals of different orientation. In a completely isotropic ma- terial, these stresses bring the material to the familiar "superplasticity" state, when the rate of strain can be described by the Cottrell formula [6] 8 where 0 is the applied stress, and GT is the yield limit of the material. However, in the case of an arbitrary polycrystalline aggregate, the dependence of the rate of plastic deformation of the crystals on stress must be a different one. The reason is that the interaction between crystals 1 and 2 differs from the interaction of crystals in a completely isotropic material. Because of the difficulties associated with attempts to take the interaction of crystallites in an arbitary polycrystal into consideration, we deal here only with the simple case when the expression can be obtained for the rate of plastic deformation, in order to illustrate the actual possibility of achieving radiation-induced growth of the polycrystal in line with the scheme proposed here. For that purpose, we consider a simplified model of a polycrystalline specimen exhibiting a certain degree of anisotropy in one of the directions. Considering only a stack of identical crystals with three principal orientations [100], [010], and [001], we represent the polycrystalline aggregate in the form of an isotropic matrix with crystals of some one orientation, say [010], "disseminated" in it. In that case, if the density of crystals having the orientation [010] in the selected direction is assigned the value n, then the density of crystals having each of the remaining orientations will be (1 - n)/ 2. The area of the transverse cross section of the isotropic matrix will therefore be 3(1 -n)S/2, and that of the "disseminated" crystals will be (3n-1)S/2, where S is the transverse cross section area of the entire specimen. Recalling that the isotropic matrix experiences no growth under irradiation, but does deform at a rate = a ?g/ crT in response to the effect of growth stresses on the part of the "disseminated" crystals, the ef- fective rate of radiation-induced growth experienced by the polycrystal can be found by solving the system: ? ? 02 ? ei+Eg = Cra F 3n 1 02-0; (1) ,g2 0. In that case the rate of deformation can be represented as the difference between the rate of deformation iso of the crystal in an isotropic medium and the rate of deformation due to restraint by two crystals having the orientations [100] and [001] (4estr): 8 = 8 iS0? 8restr, (2) grestr= estr feg. We assume that the coefficient k' is independent of the stress. We find this coefficient from the con- dition that irestr = g in the absence of external applied stress, since the crystal having the orientation [010] is then acted upon by the stress crestr = crT: Writing Eqs. (2) in expanded form, we get and hence ?k'cr,+eg-= ?8g; 2 ? k' = Ty; eg. a ? 2 ? ? eg aeg GT 3 ? k = TriT eg. In sum, the dependence of the rate of deformation of a crystal under irradiation and "disseminated" in an isotropic matrix, has the form 3 ? 81 = crieg e-F g ? Using this formula to solve system (1), we get 3 ? 41. 62 ? ? aieg. + 4,8g = ? Eg? aT aT Cr20.83. s It is interesting to note that if the Cottrell formula is used in the case of rate of deformation of irradiated crystals "disseminated" in an isotropic matrix, the solution of the system of equations (1) for the radiation growth coeffi- cient of the polycrystal will become G. 3n -1 G. poly 2 isg A similar expression for Gipoiy can be derived, with this model of a polycrystalline specimen, when we resort to the procedure of calculating the x-ray growth index [1] and the growth index based on combined measurements of the linear expansion coefficient and the electrical resistivity [2]. By relying on a rough approximation which leaves the complicated nature of the interaction of crystals in the polycrystalline spec- imen out of account, we can derive expressions for the growth indices currently in use. Figure 1 shows a predicted Gipoiy curve obtained by using Eq. (3) at Gisg = 1000. We make use of measurements results at 80?C borrowed from [5] to afford a comparison between predicted and experimental cripoly values. The texture of the specimens was brought about by different cold deformation of uranium wire previously quenched from the 3-phase. In this case, it appears that we can anticipate formations of the simplest texture, one analog of which is the model of a polycrystalline specimen used in the work de- scribed here. Experimental values were plotted together with the predicted theoretical curve in Fig. 1. The agreement between predicted and experimental values is reasonably satisfactory. In particular, the predicted growth coefficient in the region of small textures increases to a slighter extent, and in the region of large textures to a greater extent, than the linear dependence indicates. When n 0.83, the radiation growth coefficient of the polycrystalline uranium attains values typical of a single crystal. Consider some of the remarks relating to the proposed mechanism of radiation-induced growth of the polycrystalline a-uranium. The expression for the rate of Cottrell creep was used for the quantitative cal- culations of Gipoiy at the irradiation temperature 80?C; Anderson-Bishop analysis [7] can be used in the case of higher temperatures. In both cases the polycrystalline aggregate is treated as an assemblage of distinct crystals whose properties determine the properties of the polycrystal. This explains the need to take that factor into account in the case of irradiation of polycrystalline uranium in the temperature range where intercrystal effects begin to play a role. An idealized model of a polycrystalline aggregate was selected for quantitative calculations of the radiation growth coefficient of polycrystalline uranium with a different degree of texture definition. Clearly, in a real uranium polycrystal the distribution of the poles of the principal crystallographic directions will differ from the one considered here. The radiation growth coefficient of polycrystalline uranium calculated on the basis of Eq. (3) might consequently differ from the one measured experimentally in the case where a different relationship prevails between the density of the poles [100] and [001]. The theoretical growth co- efficient will be somewhat too high, if the density of the [100] poles is greater than the density of the [001] poles, and will be somewhat too low if the density of the [100] poles is lower than the density of the [001] poles. Nevertheless, the discussion of the simple model of a polycrystalline aggregate does prove useful for throwing light on the overall regularities of radiation-induced growth in polycrystalline uranium. 326 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 With those remarks in mind, we can draw the following inferences with the aid of the proposed mech- anism, in analyzing the possibility fhat radiation-induced growth of polycrystalline uranium will occur. 1. Radiation-induced growth of polycrystalline uranium must be described without assuming mutual reorientation of the component crystals, and while taking as point of departure the presence of internal stresses generated by the interaction of differently oriented crystals subjected to irradiation. These con- cepts can then be used subsequently in quantitative calculations of the effective radiation growth coefficient of polycrystalline uranium specimens, in a manner similar to the procedure followed in the simplest case, provided formulas describing deformation of the crystal under conditions where radiation-induced growth is restrained to different extents are derived. 2. The radiation growth coefficient of polycrystalline a-uranium is a nonlinear function of the degree of initial anisotropy of the material. Conclusions on the effect of alloying on radiation-induced growth of uranium single crystals, obtained on the basis of linear extrapolation of the results obtained for weakly textured specimens [3, 4] must not be accepted as sufficiently validated, for that reason. 3. Radiation-induced growth of polycrystalline uranium is associated with the generation of internal stresses, which at the same time constitute the primary cause of accelerated creep in irradiated uranium. Deformation of polycrystalline uranium due to the combined effect of texture and an external applied load cannot be treated, consequently, as the result of a simple superposition of those phenomena. LITERATURE CITED 1. E. Sturcken and W. McDonnell, J. Nucl. Mat., 7, 85 (1962). 2. J. Stobo and B. Pawelski, J. Nucl. Mat., 4, 109 (1961). 3. W. McDonnell et al., J. Inst. Metals, 97, 26 (1969). 4. J. Lehman et al., Radiation Damage in Reactor Materials, Vol. II, Vienna (1969), p. 413. 5. S. Buckley, Institute of Metals, Symposium on "Uranium and Graphite," Paper No. 6, London (1962). 6. A. Roberts and A. Cottrell, Phil. Mag., 8, 711 (1956). 7. R. Anderson and J. Bishop, Institute of Metals, Symposium on "Uranium and Graphite," Paper No. 3, London (1962). 8. A. S. Zaimovskii et al., 2nd Geneva International Conference on the Peaceful Uses of Atomic Energy, 1958, Report No. 2191 (USSR). 327 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 CALIBRATION OF GAMMA ? GAMMA DENSITOMETERS K. Umiastowski UDC 550.83 The gamma?gamma method, which is one of many geophysical methods of investigating the proper- ties of rocks, is based on measuring the intensity of gamma radiation scattered in the medium. Depending on the relative position of the radiation source, the detector, and the investigated medium, one distinguishes between 27r geometry, 4r geometry, and 27r borehole geometry (Fig. 1). The results of gamma? gamma measurements are used to determine the rock density, the effective atomic number (Zeff), and the content of heavy elements. The gamma? gamma method should be used only for density studies even if the obtained results are usable also for other cases. Calibration Curve for Gamma?Gamma Densitometers. According to the principle of similitude [1, 2], the radiation intensity I, measured at a distance r from the source, can be written as I (r, p,)=N f (%C) ,? (1) where r is the distance between the source and detector, p is the rock density, x = pr, N is a parameter depending on the source activity and detector efficiency, and is a parameter depending on other conditions of measurement. If the probe length is ro and if other conditions of measurement remain unchanged, the recorded radiation intensity depends solely on the density of the material: / (0= TCN I fro, P, =1\r'i (P), (2) where N' = N The curve f(p) = N*r2I(x) is called the calibration curve. It reflects the dependence of the count rate on the density of the material. The shape of the calibration curve was calculated with the aid of the Monte Carlo method [3]. The theoretical curves are shown in Fig. 2, where I denotes the number of quanta n through a unit surface S per unit time: I= a Fig. 1. Schematic representation of 27r geometry (a), 47r geo- metry (b), and 2r borehole geometry (c). (3) Institute of Nuclear Physics of the Mining and Metallurgical Academy, Cracow, Poland. Translated from Atomnaya Energiya, Vol. 32, No. 4, pp. 293-296, April, 1972. Original article submitted October 14, 1971. 328 C 1972 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 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 r21 5 4 3 2 10- 2 10- I ii Nis ..z. mI 1-- od kill _ili p -no oss- 1p. OIL 111 :a r., = = =WE= Ia inliti 70 20 30 40 50 60 x,q1cm2 Fig. 2 r2 40-3 14 i2 10 8 6 2 0 i ? x A X \ X ? ? ?,,,,,. X ? ""ii ? X 2 3 4 5 Fig. 3 6 7 x 10 Fig. 2. Theoretical calibration curve for different materials and source energies: 1) 0.66 MeV, water; 2) 0.66 MeV, aluminum; 3) 1.25 MeV, water; 4) 1.25 MeV alum- inum; 5) 0.28 MeV aluminum. Fig. 3. Theoretical calibration curves for Hg203 (s), Cs137 (A), and Co66 (x). x is ex- pressed in quantum free path units (70). The calculations were made for aluminum (Z = 13) and water (Zeff = 7.4). By expressing the distance between the source and detector in free path units (A 0) of a quantum with source energy E0, the shape of the calibration curve can be made practically independent of the source en- ergy (Fig. 3). Let us introduce the new quantity Ap = k0. The probe length is then expressed in dimensionless units = rp/ ?T. Expression (1) then becomes I = f (x, t), where the function f()4,, t) is independent of the source energy. N*r21, 410-5 12 10 8 4 2 0 A 0 2 3 4 5 7 A? ?0 '40 CUD 49 48 425 Fig. 4 Fig. 4. Universal calibration curve. x is given in 70 units. to 1.0 for Hg203 (0), 0.87 for Cs137 (A), and 1.03 for Co60 (s). Fig. 5. Energy dependence of A0, Ap, and k. 45 475 1,0 1,25 E, MeV Fig. 5 The factor N* is equal Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 (4) 329 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 1.21 102 8 6 2 101 8 6 4 X X IIII= AMINE 11=1 NMI NMI MIMI 111111111111111111 ? ? 2 4)4.. ? .k 0 ? 2 3 4 5 6 7 8 m==5- 4 Fig. 6. Universal calibration curve. Experimental data adopted from different sources: Co60 (e), Cs137 (A), Hg203 (El), and Se75 (x). By selecting proper normalization factors N, the curves for radiation sources of different energies can be superposed so that the result is a single universal calibration curve independent of the source en- ergy as shown in Fig. 4. The dependences of the 2to, A p, and k values on the y-quantum energy is shown in Table 1 and in Fig. 5. Comparison with Experimental Data. The function f(x) can be found experimentally with models of different densities p and constant probe length ro or with models of a fixed density po and probes of differ- ent lengths r. To check their validity the theoretical results were compared with experimental data. The results in [4] were obtained with a graphite model in a 21r geometry. The density of the model material was 1.75 g /cm3. The probe length varied from 20 to 60 cm. The measurements were conducted with a scintillation counter. Cs137 and Co50 sources were employed. The results of [5-8] were also considered. With properly selected normalization factors (x, expressed in A13 units), all experimental points lie on practically the same curve (Fig. 6). The data of Fig. 4 are also plotted on this figure. It is seen that the theoretical and experimental data are in close agreement. The experimental data were obtained in 27r and 27r borehole geometries. The radiation source energy ranged from ?200 keV (Se75) to 1.33 MeV (Con. Both gas-discharge and scintillation counters were used. The chemical composition of the models differed appreciably. A more detailed comparison of experimental data with expression (4) is given in [10]. Calibration of Gamma?Gamma Densitometers. The shape of the calibration curve depends on the measurement geometry, the discriminator threshold, and on the chemical composition of the medium [9]. For provisional calculations in which an accuracy better than 15% is not required one can use the theoretical calibration curve shown in Fig. 7. This curve was drawn through 80 points. To find the norma- lization factor, measurements should be made on one model only with a density pa. The factor for the given source energy (E0) and probe length r0 is then con- verted into density in accordance with the expression r2/ XpEo 10-2 (5) 8 ro 6 The use of theoretical calibration curves with probes other than those for which the calculations were originally 2 io8 6 TABLE 1. Energy Dependence of A0, A and k 13, 9 xo, g /ems X g/cms Fig. 7. 2 3 4 5 5 7 8-L Universal calibration curve for aluminum. E, MeV up 1,25 0,66 0,28 17,8 13,2 9,2 0,83 0,90 0,96 14,8 11,9 8,8 330 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 made can introduce an error not exceeding 15%. This conclusion is based on the calculation of the relative ,imean deviation of experimental dat6.. from the theoretical ones. The theoretical curve was calculated for the following conditions: 50 keV discrimination threshold, source and detector collimation angle equal to a 27r solid angle about the normal to the surface of the medium, detector efficiency equal to 100% and inde- pendent of radiation energy. If higher accuracy is required for probes of different construction, the calibration curve must be found experimentally. This can be made with a small number of models provided gamma radiation sources of dif- ferent energies are used. The calibration curve can be plotted for a wider range of densities than those of the models available. The calibration procedure is explained below using a specific example. Let the probe length be r = 20 cm, and let models have densities p = 1.5, 2.0, and 2.5 g/cm3. Using these models with a Cs137 source (E0 = 0.66 MeV, Ap = 11.9 g/cm3) we obtain intensities at points corresponding to xi = 2.52, X 2 = 3.36, and x3 = 4.2 calculated from roP x ? Xp (E) ? Then, using a Co60 source (E0 = 1.25 MeV, )p = 14.8 g/cm3) and a Hg203 source Op = 8.8 g/cm3), we ob- tain I at the points 4.4 = 2.03, x5 = 2.70, x 6 = 3.38, x7 = 3.40, x8 = 4.54, and x9 = 5.68. The values of I at the points x2, x 6, and 3t7 are used to normalize the results obtained with three different sources (since it is practically impossible to find sources of the same activity). Converting then x into densities p for a cesium source in accordance with xXP 11.9 g/cm3 ? P 7.0 20cm ' we obtain finally p4 = 1.21, p5 = 1.61, p6 = 2.01, p7 = 2.02, p5= 2.7, and p5= 3.37 g/cm3. Thus, using three models with densities between 1.5 and 2.5 g/cm3, we obtained seven points on the calibration curve corresponding to densities between 1.21 and 3.37 g/cm3. A second densitometer calibration technique follows from the expression [11]: 3,5 Ab (pr) sn ?aPr?biZeq e (6) where Ab, n, a, 131 are factors that depend on the conditions of measurement. Substituting into this expres- sion pr =X P X we have (AbXn) ?(cck yx?biZ3'5 xne P cq Denoting (Ab Aril) = A, a Ap = B, and equating (8) with (1), we have f(u) = xne?Bx?bi4e (7) (8) (9) The factors n and B do not depend on the source energy as the function f(x) is valid for any source energy. Finally, the intensity of recorded radiation is expressed as I e?B x? 61445 ? Axn (10) r2 where the factors n and B depend only on the probe construction and do not depend on the radiation source energy. The factors A and b1 depend on both the probe construction and the source energy. Making measurements on Nm models and using Ni sources with different energies we should find 2Ni + 2 factors in (10) (the two factors B and n, and also the two factors A and b1 for each source). These fac- tors are found from NinNi measurements. Hence follows the condition or NmNi >2Ni+ 2 2 Nin >2+ Ni ? (11a) 331 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Thus, at least four models are required if only a single source is available for the unknown factors. If the calibration is made with two sources, the number of models necessary is reduced to three. Obviously, the use of several gamma radiation sources with different energies allows a significant improvement of the calibration curve accuracy (provides a greater number of calibration points with the same number of models), and makes it possible to plot the calibration curve for a wider range of densities than that of the models employed. LITERATURE CITED 1. Sh. A. Guberman, At. Energ., 10, 369 (1961). 2. J. Czubek, Report CEA-R 3099 (1966). 3. K. Umiastowski, Nukleonika, 15, No. 1, 37; No. 2, 215; No. 3, 259 (1970). 4. K. Umiastowski, Report CEA-R 4028 (1970). 5. J. Tittman and J. Wahl, Formation Density Logging (Proc. Conf. Nuclear Geophysicists), Cracow (1962), p. 339. 6. F. G. Baembitov, I. A. Gulin, and I. G. Dyatchin, Prikl. Yadern. Geofiz., No. 17, 284 (1958). 7. V. A. Artsybashev, Izv. Vuzov; Geol. i Geofiz., No. 9, 102 (1964). 8. E. M. Filippov, Prikl. Geofiz., No. 17, 231 (1958). 9. K. Umiastowski, Nukleonika, 13, No. 4-5, 413 (1968). 10. S. Rychlicki and K. Umiastowski, Nukleonika, 15, No. 1, 47 (1970). 11. J. Czubek, Report INP No. 715/1. 332 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 NEUTRON DIFFUSION IN A POLARIZED PROTON MEDIUM Yu. N. Kazachenkov and V. V. Orlov UDC 621.039.512.4 Methods have been recently developed for preparation of highly polarized (up to 80%) proton targets. Because of the strong spin? spin dependence of neutron?proton interaction the diffusion of neutrons in such media should differ from diffusion in nonpolarized targets. It suffices to say that the neutron?proton in- teraction cross section is ?3 b for parallel spins and ?38 b for antiparallel spins, and is independent of en- ergy for neutrons of up to ?60 key. This difference remains significant up to 4 MeV even if it diminishes with increasing energies. When nonpolarized neutrons are scattered on polarized protons they become partially polarized in the direction of the proton polarization vector thus reducing the scattering cross sec- tion for subsequent interactions; this means that the transparency of polarized proton shields is higher than that of similar nonpolarized shields. Let us now derive equations describing neutron diffusion in a polarized proton medium. First let us find expressions for the scattering cross section and for the neutron polarization after scattering. Before scattering the neutron and proton are described by the density matrix pin: P in = (1 ? Pioi) (1 + P2a2), (1) where p is the polarization vector, a is a vector whose components are the Pauli matrices; the subscripts 1 and 2 refer to the neutron and proton respectively. It is known that the density matrix of particles after scattering can be expressed in terms of the den- sity matrix before scattering and the interaction amplitude: Pout = Pin f + ? For energies up to -40 MeV the amplitude of neutron scattering on protons has the form [1] i= (-4-3 A + t) + (A ? f s) clia21 (3) where fs and ft is the scattering amplitude in the singlet and triplet states respectively. For neutron en- ergies up to 10 MeV, the only contribution comes from the s wave, and the triplet and singlet scattering amplitudes are written as (2) , 2i8 t i" 2ik where k is the wave vector. The scattering phases obey the equation [2] 1 k2rs,t kctg6? as, t 2 ' (4) (5) where as, t is the scattering length, and rs, t is the effective interaction radius; their numerical values are given in [3]. The mean value of any operator L acting in the spin space of the exit channel is given by (L) Sp (LPout) SPPout (6) Using the expressions (1)-(4), after simple but quite time-consuming manipulations, we obtain expres- sions for the interaction cross section of polarized neutron and polarized protons, and for the polarization vector of scattered neutrons pi: Translated from Atomnaya Energiya, Vol. 32, No. 4, pp. 297-300, April, 1972. Original article submitted May 6, 1971. ? 1972 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. 333 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 da 3 1 1 = Iftr+Tlf,12+ ?4 ( I ft 12-1 isl2) (PIN); (7a) da 1 2+ Reftfs)Pi+ 1 1 Regis) P2 ?T PiTirc?r(lit1 Im f s [P1P21? (7b) lithe neutrons were not polarized before, then in the course of diffusion they can only acquire a polarization colinear with p2 (which can be easily verified considering successive collisions) and the last term in (7b) turns identically to zero. Let us divide all neutrons into those having spins parallel to p2 and antiparallel to p2. The probability of scattering with and without the change of neutron polarization can be easily determined from (7): where w++?T+wl: T w2; = I w2, W2 = I Reft fs+ 311112+1 fs12?(. I /112+ Ref tfs- 31 ft12+11812-1-( f t12?Reftfs) P2 I f t12 ?I fs II) P2 t 12? Reit f s) P2 lit 12-1/.12) Pz ? (8) (9) In (8), the first and second upper signs indicate the neutron polarization before and after scattering respectively, p2 = 1P21. In addition to protons, practical proton targets also contain nuclei of other elements whose polariza- tion, however, is so negligible [4] that they can be said to be nonpolarized. On being scattered by these nuclei neutrons are depolarized. If the neutron energy is such that the principal contribution Into scattering comes from the s wave, the probability of spin reversal by scattering on nonoriented nuclei is [5] 2 ('+l) Ip (a+?a_)2 Q = 2 bi) 3 (2/p +1) RI p +1.) af,+? I pap ' where ap+ and ap_ are scattering lengths of neutrons on the p-th isotope along channels with total spins Ip + 1/2 and Ip? 1/2 respectively, bp = Esp/Ese is the relative probability of neutron scattering on the p-th isotope nuclei except hydrogen (Elap = 1); the sum is taken over all nonpolarized isotopes in the target, Esp is the macroscopic scattering cross section on the p-th isotope, and Ese is the macroscopic scattering cross section on all isotopes with nonoriented nuclei. Let us divide all neutrons into two groups: neutrons with spins parallel to the veetor p2 (denoted by a "+" sign) and with spins antiparallel to 132 (denotedby "-"). Taking the balance of both these groups of neu- trons, and allowing for the possibility of neutrons passing from one group to the other as a result of scatter- ing, we obtain the following system of equations (scattering on the nuclei of all isotopes except hydrogen is assumed isotropic): (10) (QV) F+ (r, SZ, E) + I+ (r, E)F+ (r, g, E)= S (1W dE' (wn(E'?> x (r, E') F+ (r, E') w++ + 1;,(r, E') F- (r, fr, E') w-+] ?Ese(r, E') (1 ? Q) F+ (r, Q' E') +Ise(r E') QF- (r, E')); (5217)F- (r, E)+E- (r, E) F- (r, Q. E) = (152' dE' (E' ?? E Q' ft) x [E, (r, E') F- (r, SY, E) w-- +Es+, (r, E) F+ (r, Sr, E') W] + Ese(r, E') (1?Q) X F- (r, 52, E')+ Ese(r, E') QF (r, 51, E')) (11a) (1 lb) where E+ and E- is the macroscopic interaction cross section of each neutron group respectively, En and E-en is the macroscopic scattering cross section of each group of neutrons on oriented protons, P ; 4= Esn (1- Esti is the macroscopic neutron scattering cross section on nonpolarized protons, wn(E' E, f2' S2) is the indicatrix of neutron scattering by protons. 34 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Generally speaking, in considering the diffusion of fission neutrons in the upper energy groups one must take into account the change iri polarization resulting from spin? orbit interaction. However, as shown in [6], the corresponding corrections are quadratic with respect to the spin? orbit interaction param- eters which, in turn, are much smaller than the parameters of spin? spin neutron?proton interaction. It can be thus assumed in the first approximation that spin? orbit interaction does not affect the neutron trans- port in polarized neutron shields. As already noted before, the albedo of a polarized proton shield should be lower than that of a similar nonpolarized shield. As an example of calculating this effect we have determined the change in Keff of a plutonium slab reactor caused by polarization of a water reflector (existing polarized proton targets con- tain many crystallization molecules of water). Since the lifetime of one generation increases with reflector thickness, and since the effect is small in thin reflectors, we have selected a reflector 6 cm thick. After considering various concentrations of nuclei and different core dimensions, we have accepted the following reactor dimensions and element concentrations: 1.715 cm, dcore= ppu,?= 0.5.1024 nuclei/cm3, PBro = 0.149. 1024 nuclei/cm3, d ref= 6 cm. p016 = 0.0335 ? 1024 nuclei/cm3, --= 0.067.1024 nuclei/cm3, The first three lines refer to the core, the last three to the reflector. The calculations were made in a 26-group P2 approximation for a reactor with polarized and nonpolarized reflectors. The results indicate that Keff of the reactor with a polarized reflector is 2.7% less than with a nonpolarized reflector. The life- time of one generation / was found to be ?2 .10-8 sec. If the reactor is used in a pulse mode, the minimum halfwidth of a neutron pulse At is 1 ?sec. The numerical calculations were made by Yu. G. Kaufman. The reactivity of a reactor with a polarized proton reflector can be rapidly increased by applying a magnetic field normal to the direction of proton polarization. In such a case the spins of protons and neu- trons will start to precess in opposite directions and the nucleons will "forget" their former polarization. Let us estimate the dependence of this effect on the magnetic field. The change of the average particle momentum in the beam, and thus of the polarization p in a domain of magnetic induction B, obeys the equa- tion of motion (see, e.g., [7]) op = iPB1' (12) where y is the gyromagnetic ratio of the particle. From (12) follows that the change of the scalar product of neutron and proton polarization, pn and pp, in time is described by d (11/41)p) dt (7n ? 'VP) BiPnPpl, where yn and yp are the gyromagnetic ratios of the neutron and proton. As mentioned above, before the field is applied pn and pp are colinear; when the magnetic field is applied their precession will take place in the same plane. Thus PnPp = Pn I pp cos 0; B [pnpp] B I pnj I pp I sin 0 (13) (14a) (14b) (the field is assumed to be normal to the plane of rotation of the polarization vectors). Solving equation (13) under the conditions (14), for neutrons polarized at the instant t = 0 along Pp we have the expression PTIPP = I Pn IN COS (rn Vp) Bt. (15) 335 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 d Fig. 1. Calculation of neutron polariza- tion. As before, let us divide all neutrons into two groups: those that at the instant t = 0 were polarized along or against the direction of polarization of protons. Expression (15) then becomes PnPp =I PP I RI -4- I Pn ) COS (y?- yp) Bt - (1 -1 Pn ) COS (17? -1)p) MI. (16) The scalar product of neutron and proton polarization of the beam at a given point of space can be represented as the average scalar product of all neutrons arriving at this point and proceeding in the given direction. This circumstance makes it possible to evaluate the change in the scalar product of polarizations due to the mag- netic field. Consider an infinite homogeneous polarized medium in which there acts a magnetic field normal to the direction of polarization. Let neutrons diffuse along the x axis with a velocity v (see Fig. 1). The scalar product of neutron and proton polarization can then be written as PnPp - 00 x tiPpi [1-1-(-1)7nIPnil S d cos xx exp [?E S dx' {1+ (-1)m a [Pp I COS Zen Tn=-.0 0 0 E 0.+(-1]. pr, II S dt exp [? E S dx' {1+ (-1)m a cos ax' }1 m=0 0 0 (17) where x = tv, ?yt = (yn- yp)B/v, 3 = Ipp I / (yn- yp)B, a = p,and Ep is the macroscopic polariza- tion cross section. Solving the integrals in (17) and considering strong magnetic fields only (0 ? 1), we have PnPp 1 a Y p )2 B2I Pn I I PP I ? 4(7? y)2B 2 i I P ) I2' k Y - ? p 1+ u22:2 v2E2 (18) It should be noted that the scalar neutron and proton polarization product will decrease with increas- ing magnetic fields faster than follows from Eq. (18) since the absolute value of neutron polarization IPI also decreases. The reduction of polarization effects with an increasing magnetic field as given by Eq. (18) can be thus regarded as an upper bound. This is particularly rapid in magnetic fields for which (vn-- V p) B vl 1. In the case of a water reflector, for example, this quantity equals unity for a magnetic induction of 13,000 G and a neutron energy of -1 MeV. The design of reactors with polarized proton reflectors will certainly meet with technical difficulties (construction of large polarized targets (-1 liter), application of cryogenic techniques, use of very strong pulsed magnets). These difficulties are however not fundamental, and the parameters of a pulsed reactor should be considerably much more attractive than those of conventional reactors. LITERATURE CITED 1. V. F. Turchin, Slow Neutrons [in Russian], Gosatomizdat, Moscow (1963). 2. L. D. Landau and Ya. A. Smorodinskii, Zh. Eksp. Teor. Fiz., 14, 269 (1944). 3. V. S. Barashenkov, Interaction Cross Sections of Elementary Particles [in Russian], Nauka, Moscow (1966). 4. V. I. Lushikov, Yu. V. Taran, and F. L. Shapiro, Yadern. Fiz., 10, 1178 (1969). 5. 0. Halpern and M. Tohnson, Phys. Rev., 55, 898 (1939). 6. Yu. N. Kazachenkov, Yadern. Fiz., 1, 763 (1965). 7. Yu. G. Abov, A. D. Gul'ko, and P. A. Krupchitskii, Polarized Slow Neutrons [in Russian], Atomiz- dat, Moscow (1966). 336 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 THE ENERGY LIFETIME AND DIFFUSION OF PARTICLES IN "TOKAMAK" SYSTEMS Yu. N. Dnestrovskii, D. P. Kostomarov, UDC 621.039.643 and N. L. Pavlova In our previous papers [1-3] we studied the energy balance in a plasma on the basis of the neoclassical thermal conductivity for ions [4, 5] and a phenomenological description of the anomalous conductivity and thermal conductivity of the electrons. The results of the calculations of the ion and electron temperatures and the current-diffusion time in the plasma are found to be in good agreement with experiments. At the same time the experimentally measured energy lifetime TE turns out to be several times smaller than the calculated value. This means that an additional departure of energy from the plasma exists which was not taken into account in [1-3]. The present paper considers two models which allow the results of the theory and experiment to be re- conciled. According to the first model the additional departure of heat takes place due to the elevated ther- mal conductivity of the electrons. Since in [2, 3] the thermal conductivity of the electrons was already anomalous, such a still further elevated thermal conductivity is naturally called "superanomalous." The calculations showed that for a fixed superabnormality factor (equal to 7) the experimental and calculated values of TE coincide in a wide range of variation of plasma currents and density. According to the second model the additional energy losses take place via the ions. Whereas in [1-3] the heat exchange between ions and electrons and the thermal conductivity of the ions were considered to be classical, they are now assumed to be anomalous having the same abnormality as the plasma resistance and electron thermal conductivity. The results of calculations according to this model are also in fairly E, J W , kW /cm /cm /,5.fiet 2 1 10 20 .30 t, msec Fig. 1. Dependence of the total plasma energy E, the Joule heat W, and 00 on time for a discharge having the parameters (9). Translated from AtomnayaEnergiya, Vol. 32, No. 4, pp. 301-305, April, 1972. Original article submitted July 21, 1971. 0 1972 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. 337 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Temax Ti max T, T, msec 1000 500 0 10 20 30 t, msec Fig. 2. Dependence of the maximum ion and electron tem- peratures Ti max and Te max, the energy lifetime TE, and the particle lifetime T on time for a discharge having the parameters (9). good agreement with experiment, although the ion temperature and the diffusion time of the current in the plasma turn out to be somewhat too high. Within the framework of a phenomenological description one cannot give preference to any one model, and very sophisticated experiments are required to determine the channel of energy extraction from the plasma. Measurements of the dependence of the plasma density on time indicate that the ionization of neutrals plays a substantial role in the particle balance. In order to consider the role of neutrals the system of thermal balance equations is augmented by the equation for the neutrals in this present paper. It is shown that available experimental data on plasma density and the flux of neutrals from the walls may be reconciled with calculated data on the assumption that the nature of the diffusion of the plasma particles is neoclassical. Principal Equations In order to describe the behavior of the plasma we shall use the following system of equations in the plasma density n(x, t), a function proportional to the magnetic field of the current igx, t) = RI19/RH, and the ion and electron temperatures Ti(x, t) and Te(x, t): dn 1 d ? (xy2DS)+ P; dt dx dp, _A d r 1 d k? x ? dx L T3e/2 dx X-1.11 dr i 1 d I dT Cn dt = nx ? dx ?xnXiY' dx (Te?ri)V3H-Qi; I dT e) Cn dt 11X dx dx ) 7012 73 (7' T) nBT:1/2 [ xl ? ddx (X211)]2+Qe. Here x = r/a; A = 6.1 ? 103/a2; B = 2.107112/R2; C = 470; H is the longitudinal magnetic field in kilooersteds; R and a are the major and minor radii of the plasma torus in centimeters. D, DS, Xi and Xe denote the neoclassical expressions for the diffusion coefficient, the particle flux, and the ion and electron thermal conductivity coefficients [4, 5]. The time is measured in milliseconds, the temperature is measured in electron volts, and the density is measured in 1013 cm-3. The multipliers -y, yi, -y2, and y3 in Eqs. (1)-(4) allow a phenomenological description of the anoma- lous increase in the transport coefficients. In calculations for the abnormality of the resistance y the local 338 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 T Tern ax,"ge, eV 1000 -1 500 0 0,5 50 100 Fig. 3 msecierimax TTax eV 500 TE msec 500 20 400 MO - 10 200 100 .7, kA 0 0 10 8 5 5 2 2 Fig. 4 138 0,5 knm? Fig. 3. Dependence of the stationary values of Te max, 00, TE, and T on current for H = 25 k0e, n(0, 0) = 2. Fig. 4. Dependence of the stationary values of Te max, Ti max, )30, and TE on the plasma density for H = 25 k0e, I = 45 kA. model described in [2, 3] was used. The significance of the remaining anomalous corrections is discussed below. The quantities P. Qi, and Qe in Eqs. (1), (3), (4) describe the variations of the plasma density and of the temperature of the plasma components as a result of the ionization and charge-exchange processes: P = 60nN VT ae; Qe= ? 60N (Te?Tn) (re; Qi = ?56N (T Olf, a, +1,07 Vfecrj. Here N(x, t) and Tn(x, t) are the density and temperature of neutral hydrogen atoms in 1013 cm-3 units and electron volts; 10-160e cm2 is the cross section for the ionization of atomic hydrogen by electrons; 4 10-15 ap cm2 is the charge-exchange cross section. The system (1)-(4) was augmented by the necessary initial and boundary conditions. In particular, the boundary condition for Eq. (2) has the form ?(1, t) = 0.2RI(t)/a2H, where I(t) is the total current which was assumed to be a stipulated time function. The Distribution of Neutrals in the Plasma The complete problem involving the distribution function of neutrals in a plasma cylinder leads to a very cumbersome equation. Since, liowever, neutrals do not play a noticeable role in the energy balance of the plasma, a reasonable simplification of the problem must not lead to a radical alteration of the physi- cal picture of the process. Starting from these notions, let us consider the problem of neutrals in planar geometry rather than in cylindrical geometry. Under these conditions the solutions of these two problems on the periphery of the plasma differ little, while in the center of the plasma where the difference is sub- stantial the density of neutrals is low for a sufficiently high plasma density. Moreover, we shall assume that for charge exchange at point x at time t a neutral atom is produced having an energy equal to the ion temperature at this point and equiprobable forward and backward velocity directions. In this case we shall have the following problem for determining the distribution function of neutrals f(x, v) in the layer ?a ,,3?1p. = 260500 +74.7.T,cal/mol . Thus the partial molar enthalpy of formation of PuC13 in a fused KC1 medium in the temperature range 1083-1143?K is dilkiC13 = ?260.5 kcal/mole, and the apparent partial entropy of the reaction is ASPUC13(fus) = ?74.7 cal/deg ? mole. The heat and the entropy of the interaction of PuC13 in a mixture with fused sodium chloride are esti- mated; these are found to be equal to: AHpuci3 = ?48.3 kcal/mole, ASpuci3 =-40.7 cal/deg .mole. It is shown that the partial enthalpy of formation of PuC13 in chlorides of alkali metals increases in proportion to the increase in the radius of the salt-solvent cation. Translated from Atomnaya Energiya, Vol. 32, No. 4, p. 311, April, 1972. Original article sub- mitted August 24, 1971. 349 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 EFFECT OF OXIDATION ON STRENGTH CHARACTERISTICS OF GRAPHITE E. I. Kurolenkin, N. S. Burdakov, Yu. S. Virgil'ev, V. S. Ostrovskii, V. N. Turdakov, and Yu. S. Churilov UDC 621.039.53 The graphite stack of nuclear reactors is subjected to inevitable corrosion and erosion disintegration, which affects the period of its service [1]. The rate of oxidation is determined by a number of factors (the nature of the raw material used and its granulometric composition, thermal treatment, etc.), and during its use in nuclear reactors by the con- ditions of irradiation, i.e., the dose and the temperature. The pore structure of the graphite [2], its strength [3], electrical and thermal conductivities [4], gas permeability, etc. undergo changes. In the present work the effect of the degree of oxidation on the change in the limiting compressive strength and on the change of the volumetric weight characterizing the strength is investigated for two in- dustrial marks of construction graphite, GMZ and MPG types. The investigations have been carried out on cylindrical (0 8 x 80 mm) graphite samples which get oxi- dized in tubular electric furnace at 700?C in atmospheric air. The degree of oxidation is determined from the loss in the weight of the sample. The nature of the effect of oxidation on the change of the strength and volume weight for both original and irradiated graphite materials is illustrated in Fig. 1. The decrease in the yield point and the volume weight of graphite with the change in the degree of oxidation occurs due to the development of porosity; in fine-grain materials of type MPG the process of oxidation occurs more intensely. The change in the pore structure of graphite due to oxidation is studied by the method of small-angle scattering [5]. It is shown that the change in the specific surface of the pores is at first due to burning up of the couplings, and later (for more than 10% oxidation), when the filtration coefficient increases sharply, also due to burning up of the fillings. It is found that at oxidation temperature of 600-800?C the decrease in the volumetric weight occurs mainly in the surface layer. This agrees with the two-stage mechanism of oxidation of graphite [6], show- ing in this temperature range the process is intermediate between the kinetic (volume oxidation) and the diffusion processes. 1000 800 bo 0 500 .1400 :32,1 200 1,0 0,8 -o? 0,6 a lp,4....._.... ,e ) ? i 0/??.? p ? ? 1 ? 0 0 0,40 10 20 30 Degree of oxidation 50 1,0 47 CO 0,2 ?.... , b At' ' ? A 60 As. ? , 0 (1 A 0 ' 0 . 0 ? Fig. 1. Dependence of strength (a, b) and volumetric weight (c) of graphite GMZ on degree of oxidation (in air at 700?C) before (0) and after (e) irradia- tion at 300?C by an integral flux of 1021 neutron/cm2; MPG graphite (A); for natural graphite (0). Translated from Atomnaya Energiya, Vol. 32, No. 4, p. 312, April, 1972. Original article sub- mitted April 12, 1971. 350 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Empirical relationships, connecting the change in the compressive strength of the graphite and the volumetric weight with the degree ot oxidation, are given. LITERATURE CITED 1. R. V. Moore, H. Kronberger, and L. Grainger, II Geneva Conference (1958), Paper No. 312. 2. I. Watt and R. Franklin, 1st Geneva Conference on Ind. Carbon and Graphite, Pergamon Press, New York (1956), p. 321. 3. A. Collins et al., J. Nucl. Mater., 15, 135 (1965). 4. J. Rounthwaite, G. Lyons, and R. Snowdon, 2nd Conference on Ind. Carbon and Graphite, Pergamon Press, New York (1956), p. 299. 5. E. I. Kurolenkin, Yu. S. Virgiltev, and Yu. S. Churilov, Zh. Neorgan. Mater., 8, 80 (1972). 6. G. M. Volkov and T. V. Kotova, in: Graphite Constructional Materials, No. 4, Metallurgiya, Mos- cow (1969), p. 80. THE EQUATION OF STATE OF URANIUM HEXAFLUORIDE OVER A WIDE RANGE OF PARAMETERS V. V. Malyshev UDC 533.12 A method using a constant-volume piezometer was applied to the experimental investigation of the compressibility of uranium hexafluoride (UF6) with the density varying up to 3.417 g/cm3 at intervals of -0.1 g/cm3 and the temperature varying from 364 to 592.2?K with intervals of -10?K for the gas and -5?K for the liquid, with the pressure varying up to 242 bar. The errors in measurement were less than 0.1- 0.2% for the pressure, 0.05-0.13% for the density, and 0.07?K for the temperature. A special method was applied to remove the hydrogen fluoride from the uranium hexafluoride, and as a result the hydrogen fluo- ride content of the product investigated was less than 0.002%. The liquid - vapor equilibrium region was investigated. The experimental data for the pressure of the saturated vapor Ps, the equilibrium density of the vapor pv, and the equilibrium density of the liquid Nig were approximated, respectively, by the following equations: ig Ps (bar) = 10.5488 - 2344.4/T -0.013624T +1.0347.10-5T2; (1) (gicm3) =1.369-0.28268-0.021102+0.00503W; (2) Pliq (g/cm3) =1.369+ 0.06166 -I- 0.275702-1-0.0997503+ 0.0167704-0.00102865, (3) where TABLE 1. Values of the Coefficients bmk Value of m Value of k TABLE 2. Values of the Coefficient B 1 2 3 4 1 2 3 4 5 18,295 -41,084 133,936 -101,408 25,155 -53,108 92,104 -400,153 308,826 -74,139 50,313 -34,541 394,801 -311,388 75,528 --16,690 --39,884 --127,996 103,431 --25,397 2,368 IC cm%g KK crn3/g T., --B, crn3/g 463,3 1,036 507,9 0,841 552,5 0,675 473,2 0,983 512,9 0,832 562,5 0,626 483,2 0,939 522,8 0,794 572,4 0,608 493,0 0,892 532,8 0,763 582,3 0,561 502,9 0,862 542,6 0,724 592,2 0,533 Translated from Atomnaya Energiya, Vol. 32, No. 4, p. 313, April, 1972. Original article sub- mitted June 1, 1971; abstract submitted October 25, 1971. 351 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 8 = (504.5- T)1/3? Equation (1) describes the experimental data with an error of less than 0.3% in the 364.0-504.5?K temperature range, Eq. (2) with an error of 0.5% in the 403.7-504.5?K range, and Eq. (3) with an error of 0.2% in the 372.6-504.5?K range. The critical parameters of UF6, as determined from the expressions (1)-(3), take on the following values: pc = 1.369 ? 0.005 g/cm3, Tc = 504.5 ? 0.2?K, Pc = 46.0 ? 0.1 bar, Sc = pcTcllti/Pc = 3.55 ? 0.02, where RA = R/?. The values of the heat of vaporization, calculated from the Clapeyron ? Clausius equation by using the relations (1) and (3), were approximated by Tiezen's formula r(kJ/kg) = 128(1? 7)0406 with an error of 1.1%, where T = T/Tc. An analytical expression was obtained for the equation of state of UF6 in the form of a fifth-degree in- terpolation polynomial which had the following form for the parameters mentioned: -a--P =3.55 [1+ 2 2 birictvcirn] , C 7n (4) where 7i = P/Pc, T = T/TC, = PC/Pt and the values of the 21 coefficients bmk are given in Table 1. Equation (4) describes the experimental data with an error of 0.2-0.3% over the entire range of exis- tence of the superheated vapor (p 1.4 g/cm3) and not more than 1% for UF6 densities of up to 2.8 g/cm3. The values of the second virial coefficient B for UF6 as a function of temperature are given in Table 2. The intermolecular parameters of UF6, as calculated from the force constants of the Lennard? Jones potential (12-6), have the following values: e/k= 258 ? 6?K, 130 = 452 ? 14 cm3/mole, a = 7.10 ? 0.06 A. 352 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 LETTERS TO THE EDITOR EXPERIMENTAL STUDY OF THE PERFORMANCE OF THE RG-1M GEOLOGICAL RESEARCH REACTOR V. I. Alekseev, A. M. Benevolenskii, V. V. Kovalenko, 0. E. Kolyaskin, L. V. Konstantinov, V. A. Nikolaev V. F. Sachkov, and A. M. Shchetinin UDC 621.039.524.44 The RG-1M geological research reactor, with a thermal power rating of 30 kW, was started up in April, 1970. The fuel was 10% enriched uranium dioxide, with desalinated water as moderator and coolant. Ten vertical experimental channels are inserted in the reactor, one of them equipped with a pneu- matic shuttle. In contrast to the RG-1 reactor of similar design and 5 kW rating [1], the thermal power rating of the RG-1M reactor was brought up to 30 kW, which necessitated a change in the coolant tempera- ture control system. TABLE 1. Thermal Flux and y-Radiation Dose Rate in Experimental Devices Experimental device ,,j r-i " c?D ,r > ..4. Ifi s'j c.o 'ws'' L-- co I ,L > ill 0 ,t 'C) Thermal fluxot 8,05,52,62,62,82,6? 3,01,25,8 ? 1.0-11, neutrons /cm2 sec y-Radiation dose rate, P. 10-6, r/h 10 2,51,81,8 ? 1,8 ? 2,20,7 ? /v/A' z/ ,vigisrossnow,ci "pm airot Heat is extracted from the core of the RG-1M re- actor with the aid of a heat exchanger presenting a heat removal surface area of 2.5 m2, installed in parallel with the distillate purification system. Coolant flow through the heat exchanger is 8 m3. The results of experiments characterizing the ex- perimental capabilities of the reactor system, obtained during the startup and initial period of operation of the reactor, are cited below. Figure 1 shows a diagram of the core fueling and arrangement of the reactor experimental devices. The Key / Fig. 1. Core loading diagram; I) fuel as- sembly; II) graphite; III) vertical experi- mental channel; IV) ionization chamber channel; V) pneumatic shuttle channel; VI) photoneutron source; 1) NK-1; 2) IK-2; 3) V-4; 4) IK-3; 5) V; 6) IK; 7) PP; 8) B-4; 9) V-5; 10) V-6; 11) IK-4; 12) TsEK; 13) IK-5; 14) V-7; 15) IK-6; 16) V-1; 17) V-2; 18) V-8; 19) V-3. Translated from Atomnaya Energiya, Vol. 32, No. 4, pp. 315-316, April, 1962. Original article submitted May 11, 1971. O 1972 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. 353 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 fuel charge consists of 40 fuel assemblies (2.37 kg U235), 40 graphite push rods, and a single beryllium unit for the photoneutron source. The controlled reactivity margin of the system, with experimental de- vices not filled up, is 0.7 fleff. The total effectiveness of the two scram rods is 1.9 fleff. System subcriticality with the two scram rods fully inserted into the core, and other control components fully inserted into the core, is 3.2 3eff. Filling the other experimental devices with water has practically no effect on system reactivity. Table 1 indicates values of the thermal flux and y-radiation dose rate in the reactor experimental de- vices at the level of the core center, referred to the reactor power rating (30 kW). In the experimental arrangements of the reactor, the thermal neutron fluxes were determied by mea- suring the absolute activity of gold indicators (to a relative error of 8%) by the 13-y coincidence method; the dose rate of the y-radiation was measured to a relative error of 10%. The biological shielding of the RG-1M reactor, when the reactor is operating at 30 kW output, makes for a safe radiation environment in the reactor hall and in all the rooms adjacent to the reactor room. The unclad fuel assemblies [2] and graphite push rods used in the RG-1M reactor make it possible to set up different core and reflector configurations while the reactor is in operation. It should also be noted that, if necessary, the number of experimental channels provided with a pneumatic shuttle system for feed- ing specimens to the core and reflector can be increased. This does not mean any basic design limitations, nor any limitations from the standpoint of nuclear and radiation safety in the RG-1M reactor and environs. Operating experience has shown that the cooling system of the RG-1M reactor has important re- serves, which can be utilized in principle to increase the reactor power output to 100-120 kW with no es- sential changes in the working core loading. LITERATURE CITED 1. Yu. M. Bulkin et al., At. Energ., 21, 319 (1966). 2. Yu. M. Bulkin et al., Nuclear Research Reactor [in Russian], Avt. Svid. No. 227939, July 12, 1968. 354 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 SURFACE CONTAMINATION OF VVR-M FUEL ELEMENTS BY FISSIONABLE MATERIAL AND ITS CONTRIBUTION TO THE FRAGMENT ACTIVITY OF THE COOLANT N. G. Badanina, K. A. Konoplev, UDC 621.039.548.535 and Yu. P. Saikov One of the possible sources of the fission fragment activity of a reactor coolant is the contamination of the fuel element cladding by nuclear fuel during the manufacturing process. Under ordinary conditions of fuel element fabrication a contamination of up to 10-8 g U/cm2 is tolerated [1]. A VVR-M fuel assembly consists of three fuel elements in the form of concentric tubes (the outer being hexagonal) clad with 0.9 mm of aluminum for a total tube thickness of 2.5 mm. The surface contamination of the fuel elements for the reactor at the A. F. Ioffe Physicotechnical Institute of the Academy of Sciences of the USSR was studied by using track detectors to record the fission fragments formed under neutron bombardment [2]. By varying the integrated neutron flux this method can be used to determine surface concentrations of uranium from trace amounts in clean structural materials to pure nuclear fuel. By using an integrated neutron flux at -1012 neutrons/cm2 surface concentrations of 10-11-10-6 g U235/cm2 can be measured, with the error reaching ?70% at the limits of the interval. This method of studying surface contamination has the great advantage of permitting the determination of the spatial distribution of uranium. This can be useful in revealing the causes of contamination in the fuel ele- ment fabrication process. The recording of fission fragments by track detectors is based on the fact that a fission fragment leaves a defective region (track) which under selective etching becomes visible under a microscope. Dac- cron was chosen as a detector material since it is convenient to use on surfaces of complicated configura- tion and the technology of its manufacture eliminates the presence of heavy elements; i.e., it is a detector practically free of background [3]. The outer surfaces of the hexagonal fuel elements were examined for surface contamination. A standard with a known amount of U235 uniformly spread over an area 1 x 1 cm was attached to each face of a fuel element. The surface of the fuel element was then covered tightly with dacron 30 ? thick. The fuel element was then irradiated in a horizontal channel of the VVR-M reactor in a special device which permitted vertical displacements of the fuel element to achieve uniform irradiation over its whole height. The fuel element was irradiated for 12-16 h in a thermal neutron flux of (1-2) ? 107 neutrons/cm2. sec. After irradiation the dacron film was etched in a 40% solution of KOH at t = 60?C for 2.5 h and then washed in water and dried. This etching procedure eliminates the recording of a-particles, as was confirmed by irradiation with 5 MeV a-particles. Tracks were counted with a 90 power microscope. The U235 surface contamination was computed from N ?rn p = g U235 2 /C111, Ni where N and Ni are respectively the number of tracks on the detector taken from the fuel element area of interest and the standard; m is the U235 content of the standard. The standard usually employed has a U235 content of -.10-" g/cm2. The experimental error in determining the U235 surface contamination of a fuel element from the re- sults of a two-stage irradiation of a single fuel element was 40%. The error is made up mainly of the Translated from Atomnaya Energiya, Vol. 32, No. 4, pp. 316-318, April, 1972. Original article submitted May 18, 1971; revision submitted July 21, 1971. 1972 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. 355 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 S, cm2 180 160 140 120 100 80 60 40 20 I 1111111 IItflfl 1,10-1 1.10-10 1-78-1 n11. Fig. 1 Fig. 2 Fig. 1. Surface area S having a contamination of p g U235/cm2. Fig. 2. View of a portion of a contaminated fuel element appearing on the detector in the field of view of the microscope (a is an anomalous part). subjective error in counting tracks, the error due to the nonuniformity of the neutron flux, the statistical error, and the error in determining U235 in disseminations. After all the interesting area of the detector film (5923 cm2) was counted, a graph was plotted (Fig. 1) showing the area having a given contamination. A surface concentration of uranium in the 10-11-10-19 g U235/cm2 range is explained by the presence of uranium in the cladding material. The U235 surface contamination found in a specimen of the aluminum alloy going into the manufacture of fuel elements was 2.7 ? 10-h1 g/cm2, which corresponds to a natural uranium content in structural ma- terials of 10-6 g/g [1]. Sixty-five percent of the fuel element area examined had a rather uniform contamination over the 10-10-10-9 g 15235/cm2 range. The portions with a U235 content of more than 10-9 g/cm2 were considered anomalous and apparently arose from microdisseminations of uranium in aluminum. The a-spectrum of one such portion showed that the microdisseminations involved uranium enriched in U235. On the average 20% of the U235 on the fuel element surfaces examined was on these anomalous parts, although they occupy an area of only 3.74 cm2, which is 0.072% of the total area examined. The frequency of occurrence of disseminations, defined as the ratio of the number of anomalous portions observed to the whole fuel element area examined, is 0.05 cm-2. This implies that on the average there is one dissemination for each 20 cm2 of area. Figure 2 shows one contaminated portion of a fuel element appearing on the detector in the field of view of the microscope. To determine how strongly the contamination was fixed to the surface we rubbed the fuel assembly with a piece of wet cloth. Measurements of the surface contamination before and after rubbing showed that on the average 70% of the U235 in the dissemination was smeared over the surface. This was particularly clear on the parts with a large U235 content (over 10-7 g/cm2). In spite of the fact that smearing out and transport of contamination were observed, the change in sur- face contamination produced by rubbing the fuel elements was within the limits of experimental error. The average value of the surface contamination was determined from the histograms in Fig. 1 by -P=" E Si 1-1 356 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 where Si is the area occupied by the contamination pi, and Sn is the total area examined. The average value of the surface contamination of the fuel elements was (3.3 ?:1) ? 10-19 g U235/cm2, where the deviation is mean square. The contribution of the surface contamination of the fuel elements to the fragment activity of the cool- ant was calculated by determining the equivalent 1J235 content (Peg, g/cm2) by the relation ap B= Peq where the coefficient a = 0.5-1 takes account of the fact that some of the fragments may enter the fuel ele- ments rather than the coolant. The quantity Peg is used to characterize the fragment activity of the water in the primary loop and is determined from its rate of increase, which is a quantity equivalent to the U235 content on the fuel element surface when all the fragments enter the coolant [4]. The quantity Peg was determined from the radiochemical analysis of the VVR-M primary loop water for the sum of the isotopes of iodine, strontium, and barium during 1970; it varied from 9 ? 10-9 to 2. 10-9 g U235/cm2 from run to run. The average value of the equivalent U235 content during the year was 6 ? 10-9 g U239/cm2. The contribution of surface contamination to the fragment activity of the coolant, determined from the average value of the equivalent U235 content during 1970, was 3 1% for a = 0.5. In conclusion the authors thank D. M. Kaminker, I. G. Berzina, G. Ya. Vasil'ev, and V. A. Perely- gin for their support and assistance in the work. LITERATURE CITED V. I. Polikarpov et al., Checking the Tightness of Fuel Elements [in Russian], Gosatomizdat, Mos- cow (1962). 2. P. Price and R. Walker, ,Appl. Phys. Lett., 2, 23 (1963). 3. I. G. Berzina et al., At. Energ., 23, 520 (196-7). 4. N. G. Badanina and Yu. P. Saikov, ibid., 24, 429 (1968). 357 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 EQUIPMENT FOR STUDY OF MIGRATION OF RADIOACTIVE PRODUCTS ALONG THE CROSS SECTION OF FUEL ELEMENT A. V. Sukhikh, V. K. Shashurin, UDC 621.039.548 E. F. Davydov, and M. I. Krapivin The methods of 7-spectrometry using semiconductor detectors are well adapted to the investigation of fuel elements after irradiation. A further development of these methods is 'y-scanning of the diameter of the fuel element [1-2]. The study of migration of fusion fragments in thermal compositions at different thermal loads, the distribution of the fissionable isotopes along the diameter of the fuel element, experiments for detection of probable transfer of elements of the shell into the fuel, determination of the boundary of the fused zone from the distribution of high-melting fission fragments in ceramic fuel elements are some of the problems that can be solved with the use of spectrometric scanning of a section of the fuel element. The equipment for the investigation of the processes of migration of radioactive isotopes along the radius of the fuel elements consists of a mechanism for shifting a section of the fuel element in front of the aperture of the collimator and a y-spectrometer. The mechanism for the displacement of the section (Fig. 1) is a coordinate stand in a B-50 type box. The displacements along the horizontal and vertical planes is read with indicators with 0.01 mm divisions. The section is displaced relative to a changeable lead collimator 300 mm in length. The diameter of the collimator aperture can be changed from 0.25 to 1 mm. A semiconductor 'y-spectrometer with Ge(Li)-detector is placed on the side of the front wall of the box around the collimator. In order to reduce the y-background the detector is surrounded by a 50 mm thick layer of lead. Fig. 1. Block diagram of the equipment for y-scan- ning of the fuel element along the diameter: 1) semi- conductor Ge (Li)-detector in cryostat; 2)preamplifier; 3) amplifier-expander; 4) AI-128 analyzer; 5) power supply block; 6) protective wall of the box; 7) colli- mator; 8) mechanism for the displacement of the sam- ple. Translated from Atomnaya Energiya, Vol. 32, No. 4, pp. 318-319, April, 1972. Original article submitted June 1, 1971. o 1972 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. 358 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Fig. 2 Fig. 3 Fig. 2. Distribution of fission fragments along the diameter of the sample. (Double points on the figure are control measurements.) Fig. 3. Distribution of Cs137rover the area of the sample. The sample of the investigated fuel element, which is in the form of a cylinder with a height of 1-2 mm and with two plane parallel surfaces, is placed on a backing and is set in the displacement mechanism (the sample is prepared in a hot chamber and is led into the box along a conveyer). The distribution of fission fragments is measured by the coordinate method along the entire area of the section. The results of mea- surements are processed by the usual method, i.e., the distribution curves of given radioactive isotopes along the diameter of the fuel element are constructed. In order to illustrate the potentialities of the procedure we present the data obtained for a fuel element of 6 mm diameter with stainless steel shell and the fuel in the form of UC tablets. The thickness of the sample is 1 trim. The temperature at the center of the fuel element in the process of irradiation reached up to 1200?C, and in the shell up to 600?C. The fuel element is irradiated up to ?6% burn-up; the delay be- tween the end of irradiation and the time of measurement is ?1 year. The sample under investigation is scanned along its entire area with 0.5 mm step by a cylindrical col- limator of 1 mm diameter. The y-spectrum of the fission fragments is measured in the energy range 400- 800 keV. In Fig. 2, which shows the distribution of fission fragments along the diameter of the sample, there is a tendency for joining of the center of the element by Cs137 and Cs134 isotopes. An asymmetry of distribution of Cs137 is observed over the area of the section (Fig. 3). The obtained results confirm the efficiency of the equipment: the exposure time is about 15 min and a good reproducibility of the results is seen with an acceptable accuracy of the mechanism of the displace- ment. A further improvement of the equipment consists in the reduction of the input aperture of the coni- cal collimator to 0.1 mm and the use of coaxial Ge(Li)-detectors with large efficiency for recording y-radi- ation. LITERATURE CITED 1. Report AERE, R-5149 (1966). 2. H. Kamogama et al. (Japan), III Geneva Conference (1964), Paper No. P/430. 359 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 VACUUM-CATHODE ETCHING OF URANIUM IN VUP-2K EQUIPMENT D. M. Skorov, A. I. Dashkovskii, UDC 621.039.542.32 V. V. Volkov, and B. A. Kahn The use of vacuum-cathode etching for revealing the structure of materials is due to certain advan- tages over chemical and electrolytic etching; using this method it is possible to etch any metal and multi- phase alloys in a wide range of temperatures and also after irradiation. The form of the inclusions is re- tained in etching, which is important, for example, in electron-microscope investigation of alloys; false phases etc., do not appear in the structure revealed in etching (1-9]. Native equipment of types UVR, ITR, VUP, etc. are in serial production, which permit vacuum-cathode etching of metals including uranium. However, the use of these equipment, for example, of VUP-2K for etching uranium is beset with some dif- ficulties of constructional and procedural nature. In particular, we have found that the construction of the discharge chamber does not permit to choose the regime of operation with small current density: the dis- charge was extremely unstable and was not focussed accurately on the sample and the samples got healed in the process of etching. The oxidation of the samples is observed and etching holes appear at the sur- face. Intense pulverization of the material of the stand of the sample also occurs. In order to eliminate these drawbacks an additional inner glass cylinder 1 was placed in the discharge chamber concentric to the main cylinder (Fig. 1): the cylinder is 66 mm in diameter and 28 mm in length. As a result it is possible to obtain a stable regime of vacuum-cathode etching of uranium by argon or krypton; the voltage is 5.0 kV, current 1-3 mA, etching time 30-60 min, and the pressure in the volume of the dome about 10-4 mm Hg. For the purpose of decreasing the pulverization of the aluminum stand 2 a Teflon disk 3 with an aperture under the sample is placed or the stand is covered by niobium foil. The temperature of the stand is maintained below 0?C by cooling by liquid nitrogen, which excludes noticeable heating of the sample and shortens the etching time by several times. The termination of etching is determined from the darkening of the outer glass cylinder 4 of the discharge chamber. The hermetic sealing of the assembled system, the feed of the gas from a standard container to the inlet at a pressure of 1.5-2.5 atm, and a careful degassing of the dome and the discharge chamber of the equipment made it possible to eliminate oxidation of uranium in the process of etching. A typical form of the micro- structure of uranium after optimum vacuum-cathode etching is shown in Fig. 2. A longer-duration etching of the samples does not reveal any new details of the structure and is accompanied by unetching of the boundaries of the grains, duplicates, etc. The advantage of vacuum-cathode etching is seen especially clearly in electron-microscope investigation of the structure of ZreArA I IIIIII1 liiII A r?-?-?-?- ? -?-?- "*Wl k?????? ? n?,?A " ? .& .? ?A kt?I Fig. 1. Schematic diagram of the discharge chamber. Translated from Atomnaya Energiya, Vol. 32, No. 4, pp. 319-320, April, 1972. Original article submitted June 7, 1971; revision submitted December 2, 1971. 360 1972 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 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Fig. 2 Fig. 3 Fig. 2. Structure of uranium after vacuum-cathode etching (slant light, x440). Fig. 3. Electron-microscope photograph of angular replica taken from the surface of etched uranium. uranium (Fig. 3). The procedural and constructional recommendations given here for vacuum-cathode etching on VUP-2K equipment are appropriate even for certain alloys of uranium. LITERATURE CITED 1. N. V. Pleshivtsev, Cathode Pulverization finRussian], Atomizdat, Moscow (1968). 2. D. Armstrong, P. Madsen, and E. Sykes, J. Nucl. Mat., 2, 127 (1959). 3. T. Padden and F. Cain, USAEC Report WAPD-83 (Del.), Westinghouse Atomic Power Division (1953). 4. T. Padden and F. Cain, Metal Progress, 66, 108 (1954). 5. T. Bierlein, USAEC Report HW-32676, Hanford Atomic Products Operation (1954). 6. T. Bierlein, ibid., Report HW-34390 (1955). 7. T. Bierlein, J. Morgan, and G. Mallet, ibid., Report HW-42184 (Rev.) (1956). 8. J. Newkirk and W. Martin, G. E. Research Lab., Memo MC-24 (1957). 9. T. Bierlein and B. Mastel (USA), II Geneva Conference (1958), Paper No. 1855. 361 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 CHANGE IN THE STRUCTURE AND PROPERTIES OF TITANIUM CARBIDE UNDER THE ACTION OF IRRADIATION M. S. Koval'chenko, Yu. I. Rogovoi, UDC 669.018.4:539.2:669.01 and V. D. Kelim Extremely few studies have been devoted to the effects of irradiation on carbides [1-3]. In view of this, an experimental investigation was made of the change in the microstructure, lattice parameter, electric resistance, and microhardness of titanium carbide with the composition TiC0.94 under the action of neutron irradiation with integral doses of 1.0.1019, 3.7 ? 1019, 7.5. 10", and 1.5-102? thermal neutrons/cm2 (the ratio of the thermal neutron flux to the flux of fast neutrons is equal to 8: 1) on a VVR-M reactor at a temperature of ?50?C, as well as with subsequent annealing. Annealing of irradiated samples was conducted under a vacuum of 10-4 mm Hg at temperatures of 100-1000?C at 100?C intervals for a period of 1 h. The samples were prepared for the investigation from a powder of technically pure titanium carbide by the method of hot pressing at a temperature of 2300?C under a pressure of 240 kg/cm2, followed by electric spark cutting. Four prismatic samples with dimen- sions 2.5 x 2.5 x 10 mm, possessing the same initial state for the four selected doses of irradiation, were cut out of the hot-pressed cylindrical bullets 8 mm in diameter and10-12mmhigh. The porosity of the samples did not exceed 5%, while the average grain size was approximately 14 /I. The microhardness was 150 140 120 100 BO ar) 3000 E .2 2800 4,335 4,331 a. 4,327 4325 0 03 05 09 1,2 1,5 Intergral flux, ? 1020 neutrons/cm2 Fig. 1 Fig. 2 Fig. 1. Change in the lattice parameter and properties of the carbide TiC0.94 during neutron irradiation. a 0 Fig. 2. Diffraction effects in the carbide TiC0.94: a) before irradiation, after irradia- tion with doses (neutrons/cm2); b) 1.0 ? 1019; c) 3.7 ? 1019; d) 7.5 ? 1019; e) 1.5.1020. Translated from Atomnaya Energiya, Vol. 32, No. 4, pp. 321-323, April, 1972. Original article submitted June 3, 1971; revision submitted October 3, 1971. 362 CD /972 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 2013/03/01 : CIA-RDP10-02196R000300100004-7 "8 Zz 3500 3200 2800 0; a) Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 - 150 - 130 110 90 TABLE 1. Activation Energy and Kinetic Parameters in the Annealing of Irradiated Titanium Carbide T, ?C Homologous temperature F. eV Ko, sec-1 350 0,18 0,26 7,7.10-3 600 0,25 0,40 2,0.10-2 measured on a PMT-3 instrument according to 50-100 im- prints. Metallographic investigation was conducted on an MIM-8M microscope, and x-ray diffraction study on a URS- 50-IM diffractometer. The specific electric resistance was measured by a compensation method according to a two-probe circuit. Metallographic investigation did not show any change in 70 the average grain size of the samples after irradiation, as well as subsequent annealing. After irradiation with a dose of 1.5-1020 neutrons/cm2, an increase of 0.3-0.5% in the volume of the sample was ob- served. Irradiation led to a substantial increase in the elec- tric resistance of the lattice parameter of the carbide (Fig. 1); after a dose of 7.5.1019 neutrons/cm2 this increase was sharply reduced. A regular shift of the diffraction peaks in the direction of smaller angles with a simultaneous decrease in their intensity is observed (Fig. 2), along with an improve- ment of the degree of resolution of the a-doublet on the line (333). After annealing at 100?C (Fig. 3) there was an increase in the lattice parameter, accompanied by a decrease in the intensity of the line (111) and especially for (200). At temperatures of annealing 200-800?C, the lattice parameter systematically decreased. The intensity and resolution of the a-doublet of the line (333) was unchanged after all stages of annealing of TiC0.94, remaining rather high. The lines (111) and (200) were distinguished by a substantial and almost unchanged intensity after annealing of the samples at temperatures above 100?C. Other than a 15% increase after annealing of the samples at 300?C, the micro- hardness did not undergo any significant changes (Fig. 3). A complete recovery of the supplementary elec- tric resistance induced by irradiation occurred at 650?C. According to the data of annealing, we can distinguish two stages of recovery ? at the temperatures 350 and 600?C, whereas the expected temperature of the beginning of migration of vacancies in titanium carbide according to a composition close to stoichiometric is ?750?C [2]. Qualitatively close data were obtained in the annealing of uranium carbide [1], where two stages of recovery were established: around 200?C and between 400 and 600?C. 50 0 200 400 600 BOO 1000 Temperature of annealing, ?C Fig. 3. Isochronous recovery of the lattice parameter and properties of the carbide TiC0.94, irradiated with a dose of 1.5 ? 1020 neutrons/cm2 at a temperature of ?50?C. A quantitative evaluation of the results of annealing (see Table 1) was performed according to the data of the recovery of electric resistance using the kinetic equation: dC ?e ?E/hT dt where C is the concentration of defects; E is the activation energy; y is the order of the reaction; Ko is the kinetic coefficient [4]. A substantial increase in the lattice parameter with a simultaneous decrease in the intensities of the lines without any appreciable broadening of them, as well as the linear variation of the electric resistance of the carbide up to a dose of 7.5 ? 1019 neutrons/cm2, permit us to assume that after irradiation, chiefly point defects remain in TiC0.94. The diffraction effects in the samples, due to a dose of 1.5.102? neutrons / cm2 (see Fig. 2e) as well as the absence of appreciable strengthening (according to the data of microhardness), 363 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 permit us to assume the occurrence of a process of annihilation of defects, since a strengthening of the material and a broadening of the x-ray reflections would be observed if accumulations of defects were formed. The increase noted in the lattice parameter of titanium carbide after annealing at 100?C may evidently be associated with a "recovery" of the dynamic crowdions during thermal activation [5]. We may also as- sume a relaxing shift of the carbon atoms, leading to a more substantial change in the contour of the line (200) in comparison with the line (111). Such a conclusion is based on the fact that the plane (100) in TiC is a cleavage plane [6, 71, with a tendency to decoration by carbon [7]. The relaxing movement of the in- terstitial atoms, scattered close to dislocations, with deposition on the latter, may explain the increase in the microhardness when the temperature of annealing is increased to 300?C. The stage of recovery at 350?C is also evidently associated with the movement of carbon atoms, i.e., with recombination of the in- terstitial carbon atoms with vacancies. It may be assumed that this recombination occurs according to a mechanism of transition of carbon atoms from tetrahedral vacancies to octahedral vacancies, as a result of which there is a decrease in the lattice parameter. The decrease in the microhardness at this stage may be caused by a liberation of point defects from dislocations. The stage of annealing at 600?C should evidently be ascribed to recombination of the interstitial titanium atoms with vacancies. At this stage the lattice parameter is changed to a greater degree (see Fig. 3). The similarity of the mechanisms of annealing at both stages is confirmed by the closeness of the kinetic coefficients and the values of the activation energy (see Table 1). The first order of the reaction, due to recombination of interstitial atoms chiefly with the closest vacancies [8, 9] also does not contradict the mechanism noted. The improvement of the degree of resolution of the of-doublet on the line (333) after irradiation of the carbide is evidence of a decrease in the microstresses, apparently as a result of capture of interstitial atoms in the disturbed regions of the lattice and in submicropores, present in hot-pressed samples of titan- ium carbide [2]. This agrees with the nature of the change in the microhardness, as well as with the de- crease in the microhardness and with the lag in the change in the lattice parameter in the carbide after ir- radiation with a dose of 1019 neutrons/cm2. LITERATURE CITED 1. B. Childs and J. Ruckman, New Nucl. Materials Including Nonmetallic Fuels, Vol. 2, Vienna, IAEA (1963). 2. M. S. Koval'chenko and V. V. Ogorodnikov, Poroshkovaya Metallurgiya, No. 10, 48 (1966). 3. G. Keilholtz, R. Moore, and M. Osborne, Nucl. Applications, 4, 330 (1968). 4. M. Balarin, R. Rattke, and A. Zetsche, Auswertungsmethoden f?r Erholungsvorgange, Zentralin- stitut fiir Kernforschung Dresden (1966). 5. S. T. Konobeevskii, Effects of Irradiation on Materials [in Russian], Atomizdat, Moscow (1967). 6. W. Williams, J. Appl. Phys., 32, 552 (1961). 7. S. E. Brooks, Special Ceramics (Transactions of the Symposium of the British Ceramic Society) [Russian translation], Metallurgiya, Moscow (1968), p. 90. 8. A. Damask and J. Deans, Point Defects in Metals [Russian translation], Mir, Moscow (1966). 9. M. Thompson, Defects and Radiation Damages in Metals [Russian translation], Mir, Moscow (1971). 864' Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 Declassified and Approved For Release 2013/03/01 : CIA-RDP10-02196R000300100004-7 CHANGE IN THE DENSITY OF SINGLE-CRYSTAL TUNGSTEN DURING NEUTRON IRRADIATION V. N. Bykov, G. A. Birzhevoi, UDC 621.039.531:669.27 and M. I. Zakharova The investigations were conducted on single-crystal samples of tungsten, produced by electron beam zone melting [1]. The quality and perfection of the single crystals were monitored by an x-ray method and by selective etching. The dislocation density was 5 ? 105 cm-2, angles of disorientations from 30" to 30'. The samples for irradiation were cut out from the middle portion of a single-crystal rod. The results of spectrochemical analysis are cited in Table 1. To remove the cold-hardened layer the samples were treated electrolytically in a 2% solution of KOH under a voltage of 14 V and a current of 5 A. The removal of the cold-hardened layer was monitored according to the width of the x-ray diffraction line; the depth of the removed layer was 200 ?. The finished samples had a length of 25 mm, and a dia- meter of 2.5 mm. Ad1,2 T100 49 46 0,3 0 04 500 0,24 1000 1500 2000 1?C 0135 0,451,?K Tm Fig. 1. Curve of restoration of den- sity in isochronal annealing of tungsten single crystals, irradiated with a dose of 1.4.1022 neutrons/cm2 at 0.20-0.21 Tm. Irradiation was conducted in hermetically welded ampoules at the temperature 450-500?C (0.20-0.21 Tm) with an integral flux of 1.4 ? 1022 neutrons/cm2 (4 .1021 neutrons/cm2, E > 1 MeV). After irradiation the samples were washed in a mix- ture of hydrofluoric and nitric acids, then electrolytically polished. As a result of such treatment the surface layer, contaminated by radioactivity during the finishing of the am- poules, was removed. The samples were annealed in a vacuum furnace in the temperature range 500-2200?C for 1 h at a residual pressure of no more than 5 ? 10-5 mm Hg. The density was determined by a hydrostatic method [2]; calculation was performed according to the formula TABLE 1. Results of Spectrochemical Analysis d PQ (6 X)??, Element Zr Nb Ta Ti Mo Fe Mg Mn Pb Cr Ni Amount, %by weight
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