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SOVIET ATOMIC ENERGY VOL. 44, NO. 5

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CIA-RDP10-02196R000700110004-2
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November 1, 1978
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Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 ? ISSN 0038-531X Russian Original Vol. 44, No. 5, May, 1978 ; November, 1978 SATEAZ 44(5) 457-560 (1978) , \ SOVIET ATOMIC ENERGY ATOMHAR 3HEP1HR (ATOM NAVA ENERGIYA) TRANSLATED FROM RUSSIAN CONSULTANTS BUREAU, NEW YORK - \ Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 SOVIET ATOMIC ENERGY Soviet Atomic Energy is abstracted or in- dexed in App/id Mechanics Reviews, Chem- ical Abstracts, Engineering Index, INSPEC? Physics Abstracts and Electrical and Elec- tronics Abstracts, Current Contents, and , Nuclear Science Abstracts. Soviet Atomic Energy is a c'over-to-cover translation of Atomnaya Energiya, a publication of the Academy of Sciences of the USSR. 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Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 SOVIET ATOMIC ENERGY A translation of Atomnaya Energiya November, 1978 Volume 44, Number 5 May, 1978 OBITUARIES CONTENTS Engl./Russ. Academician G. I. Budker ? I. N. Golovin 457 395 ARTICLES The Gyrocon, a Highly Efficient Converter of Energy from Powerful Relativistic Beams for Microwave Supplies in Charged-Particle Accelerators ? G. I. Budker, M. M. Karliner, I. G. Makarov, S. N. Morozov, 0. A. Nezhevenko, G. N. Ostreiko, and I. A. Shelditman.. ? ? ? 459 397 Industrial Electron Accelerators Designed at the Institute of Nuclear Physics, Siberian Branch, Academy of Sciences of the USSR ? V. L. Auslender and R. A. Salimov ? ? 466 403 Gas Porosity Arising on Annealing Irradiated Beryllium ? g. Ya. Mikhlin and V. F. Chkuaseli ? ??? ???? 472 409 The Effect of a Horizontal Shift of the Regulator ? E. A. Garusov.. 475 411 Separate Determination of Local Levels of Boron and Lithium in Minerals, Rocks, and Ores ?I. G. Berzina, A. S. Dzhamalov, A. V. Drushchits, V. S. Kulikauskas, S. V. Malinko, and A. F. Tulinov.. 483 418 Solvent-Extraction Equilibria in Reprocessing Fast-Reactor Uranium?Plutonium Fuel ?V. E. Vereshchagin and E. V. Renard. ???? 487 422 Energy Balance in a Tokamak Reactor with Turbulent Transport Coefficients ? V. K. Kolesnikov, V. G. Petrov, and V. D. Khait ? ? ? 492 428 Tritium in Atmospheric Precipitations, Rivers, and the Seas in and Around the USSR Territory ? S. M. Vakulovskii, A. I. Vorontsov, I. Yu. Katrich, I. A. Koloskov, F. Ya. Rovinskii, and E. I. Roslyi . 497 432 Fire Safety and Explosion Proofness of the Bituminization Process ? K. P. Zaldiarova, V. V. Kulichenko, E. R. Mazin, Yu. N. Sadovnikov, and 0. V. Ukke 501 436 Deactivation of Steam Generators of Novovoronezhskaya Atomic Power Plant ? L. I. Golubev, V. F. Lyukov, I. M. Plotnikov, V. K. Sedov, A. A. Smirnov, and A. F. Sotnikov 504 438 The Production of Tritium in Fission and Fusion Reactors ? V. G. Vasil'ev, Z. V. Ershova, and E. V. Dmitrievskaya ? ? 507 440 Content of Uranium Isotopes and Transuranium Elements in the Spent Fuel of a VVg11-365 Reactor ? V. Ya. Gabeskiriya, V. V. Gryzina, A. A. Zaitsev, V. V. Mikulenok, 0. A. Miller, Yu. B. Novikov, V. G. Polyukhov, G. N. Robulets, V. V. Tikhomirov, A. P. Chetverikov, and G. N. Yakovlev... 513 446 BOOK REVIEWS Yu. E. Kreindel' ? Plasma Electron Sources ? Reviewed by E. G. Krastelev 516 450 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 CONTENTS DEPOSITED PAPERS Calculation of Absorbed Dose in Some Problems Of TwO-DimensiOnal 'y-Radiation Transport - Yu. I. Chernukhin, Yu. N. Lazarev, A. I. Orlov, and N. L Ivanova .?.???? ? ? ? Using a Porous Metallic Silver Electrode to Determine Microconcentration of Chlorine Ions in Water Coolants on Nuclear Power Plants - L. N. Moskvin, N. Ya. Vilkov, and V. M. Krasnoperov... Approximation of Optimal Control of Xenon Transient Processes - A. S. Gerasimov . . !continued) Engl./Russ. 518 451 519 451 519 Application of Ge(Li) Detectors for y-Ray Spectroscopic Analysis of Environmental Samples - E. G. Tertyshnik, L. P. Bochkov, and S. M. Vakulovskii ? ? ? 520 453 Peculiarities of the Variations in the Electrical Conductivity of Organic Dielectrics under Pulsed Gamma-Neutron Irradiation - A. A. Shluirpelov, A. P. Elokhin, and S. N. Makeev ? ? 521 453 BOOK REVIEWS F. Ya. OvehlruaikoV, L. I. Golybev, V. D. Dobrynin, D. I. Klochkov, V.V. Semenov, and V. I. Tsybenko. Operating Conditions of Water- Moderated-Water-Cooled Power Reactors - Reviewed by V. I. Pushkarev 522 454 LETTERS Error of Calculation of Composition in Nondestructive Analysis of Nuclear Fuel - A. K. Sheremet'ev ? ? ? ? ? 524 455 - Calculation of Shielding Made of Concrete with an-increased Hydrogen - Content -V. V. Belyakov, V. A. Grigor'ev, P. A. Lavdanskii, O. A. Remeiko, and V. F. Khokhlov 526 456 Study of Neutron Fields in Channels of Ionization Chambers of Water-Moderated-Water-Cooled Power Reactors - L. I. Golubev, A. M. Berezovets, A. N. Eremin, E. M. Ignatenko, A. G. Inikhov, V. P. Kruglov, V. I. Lobov, S. S. Lomakin, G. G. Panfilov, V. I. Petrov, and V. V. Fursov ? ? ? 528 458 Depth Distribution of the Color Centers in Glasses Irradiated with Electrons - A. P. Balashov, Yu. B. Govyadovskii, V. F. Kosmach, and V. I. Ostroumov ? ? 530 459 The Effect of Additional Moderation of Neutrons in a Heterogeneous Cell with a Scatterer - I. I. Zakharkin, V. A. Kuznetsov, I. E. Somov, and L. A. Chernov 532 461 Variation of the Radiation Dimensional Stability of Structural Graphite - Yu. B. Virgil'ev, I. P. Kalyagina, and G. G. Kireeva 534 462 Temperature 'Distribution in the Radiation Head of a Gamma-Teletherapy Unit - A. G. Surkin, G. P. Elisyutin, and M. Sh. Vainberg 536 463 INTERNATIONAL COOPERATION .Soviet-Japanese Cooperation on the Peaceful Uses of Atomic Energy - B. A. Semenov 539 465 CONFERENCES, MEETINGS, AND SEMINARS International Seminar on the Technology of Sodium Coolant - V. I. Kondrat'ev and Yu. V. Privalov 541 466 IAEA Activities on High-Temperature Reactors - V. N. Grebennik.... 542 4,67 Meeting of IAEA Experts on Thermonuclear Reactors - G. N. Popkov. . ? ? ? 544 468 Seventh International Conference on Atomic Collisions in Solids -Y. M. Chicherov 545 469 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 CONTENTS (continued) Engl./Russ. First International Seminar on Use of Proton Beams in Radiation Therapy 547 470 IAEA Meeting on the Use of Physical Standards ? P. I. Fedotov 548 471 All-Union Seminar on the Processing of Physical Information ? 0. P. Fedotov. 549 472 International Congress on Concentration of Useful Minerals ? I. P. Kondakov 551 473 Meeting of IAEA Consultants on the Choice of Sites for Burial of Radioactive Wastes ? M. K. Pimenov 553 474 Meeting of IAEA Experts on Protection of Population in Major Radiation Accident ? Yu. V. Sivintsev and V. A. Klimanov 554 475 IN THE INSTITUTES Methods of High-Energy Plasma Technology ? V. G. Padalka and V. T. Tolok 556 476 BOOK REVIEWS A. P. Shirenko ?Radioisotopic Methods of Measuring Altitudes ? Reviewed by E. R. Kartashev 559 478 The Russian press date (podpisano k pechati) of this issue was 4/22/1978. 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 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 OBITUARIES ACADEMICIAN G. I. BUDKER I. N. Golovin May 1, 1978, would have been the 60th birthday of Academician Gersh Itskovich Budker, the leading Soviet physicist known throughout the world for his researches on charged-particle accelerators and controlled ther- monuclear synthesis. He died on July 4, 1977, of major heart disease while still full of energy, both mental and physical. G. I. Budker was born in the village of Muraf in the Shargorod area of Vinnitsa Oblast, and in 1941 he graduated from the Physics Faculty at Moscow State University; he served until the end of the war in the Army Air Services Branch in the Far East, and on demobilization in the summer of 1945 started work at the Institute of Atomic Energy, which was then called the No.2 Laboratory of the Academy of Sciences of the USSR. I. V. Kurchatov directed him in the analysis of some urgent questions at that time. These particularly concerned the motion of charged particles in cyclotrons, followed by control theory for uranium?graphite reactors. How- ever, he is particularly remembered for his outstanding work in the early days of controlled thermonuclear reactions. As early as 1952 he put forward almost simultaneously two outstanding ideas; magnetic traps for retaining thermonuclear plasma and stabilized electron beams, with the latter subsequently utilized in the con- struction of a new type of charged-particle accelerator. A laboratory of new acceleration methods was set up in 1954 to implement his ideas on accelerators. In 1956 he presented his DSc, and in 1958 he was elected a Corresponding Member of the Academy of Sciences of the USSR, and in 1964 as a full Academician. From the end of 1957, with the support of I. V. Kurchatov, he participated in setting up the Institute of Nuclear Physics, Siberian Branch, Academy of Sciences of the USSR in Akademgorodok. He was the Director of this institute until his death, and he converted the institute to a Translated from Atomnaya nergiya, Vol. 44, No.5, pp. 395-396, May, 1978. 0038-531X/78/4405-0457$07.50 ?1978 Plenum Publishing Corporation 457 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 major nuclear physics research center, which has become recognized throughout the world as performing unique scientific?engineering researches. Throughout these years he participated in numerous conferences on high-energy physics and accelera- tors, plasma physics, and thermonuclear synthesis not only in the USSR but also abroad, andhe had consider- able influence on the development of researches in these areas throughout the world. His outstanding scienti- fic researches were recognized in the award of Lenin and State Prizes, as well as medals and other orders. From his early days he was accustomed to fundamental research into intricate problems in physics. He had a masterly way of resolving the paradoxes that frequently arise in careful examination of physical phenom- ena. He repeatedly emphasized that the physicist has no right to say that no result was obtained even if the result of an experiment was negative, since he is obliged to define the laws of nature that explain his negative results. In his own researches he encountered many different obstacles, for which he always invoked novel solutions, which, particularly in his early years, were sometimes dismissed as unfeasible fantasies. How- ever, when it became clear that these ideas,were always feasible, these skeptical evaluations were replaced by international recognition. Many of Budker's ideas were ahead of his time. His concept of a stabilized electron beam provided access to a new area of high particle energies, and this attracted immediate attention and formed the basis of various researches here and abroad. However, Budker himself immediately recognized that the technology was not yet available to implement it fully, and therefore even in the early 1960s he concentrated the efforts of his institute on the colliding-beam concept for research on elementary-particle interactions at superhigh energies. Although the colliding-beam concept was not his own, he applied to its implementation some extremely original ideas, such as storage rings for exam- ining electron?electron and electron?positron interactions ranging from the VEP-1 to the recent VPPP-4, which have considerably advanced this area of engineering. The VPPP-2 storage rings and the high-current VAPP-2M made a major contribution to elementary-particle physics, particularly to the determination of the exact mass and peak width in vector-meson decay, as well as the branching probability in such decay. The V.6PP-3 is now a powerful source of synchrotron radiation and is used by institutes in this country, in parti- cular for research in molecular biology. The constructors of the VPPP-4 had the foresight to provide facili- ties for raisins the electron-beam intensity; the positron injector should be completed in the summer of 1978, and then the VEPP-4 will constitute a world leader in systems of this type, since it will allow one to examine the interaction of electrons with positrons at collision energies up to 14 GeV. The plan for Soviet?American collaboration in this area includes utilization of the facility by a group of researchers from Stanford. The VPPP-4 required a high-frequency oscillator in the meter wavelength range working in the steady state at an output of several megaelectron volts; traditional tubes would have been difficult to employ, and Bud- ker, as an experimental relativistic engineer, suggested a novel solution, namely a novel form of generator called a gyrocon, which uses a relativistic electron beam of energy 0.5 MeV to excite a cavity. The VAPP-4 ring was designed to store proton?antiproton beams; a store of this type requires a very small phase volume for the particles in a captured bunch. Various solutions to this problem are being exam- ined in laboratories throughout the world. In 1967, Budker suggested the idea of electron cooling and confirmed its performance by experiment. It is now proposed that this method will be used in antiproton storage rings. In the area of thermonuclear work, Budker developed at his institute only those lines that did not dupli- cate Soviet or foreign researches. He halted extension of researches on accelerators begun so successfully in the institute in the mid-1960s, since other laboratories were working in this area, and instead gave vigorous support to a mirror system in which a dense plasma was heated by a relativistic beam. The plasma pressure is contained by the wall in this system, while the magnetic field merely reduces the transverse thermal conduc- tivity, and the multiple magnetic mirrors hinder the plasma from escaping along the tube. During his last months, he was working on an experimental test on plasma retention by an ambipolar potential formed in an open trap with two mirrors. This idea has given new life to open traps as major forms of thermonuclear reac- tor. It is here in place to recall that in 1968 the International Atomic Energy Agency held an international con- ference in Novosibirsk on thermonuclear researches. Here Budker issued a challenge to initiate engineering developments on reactors on the basis of the available physical knowledge. The participants were thrown into some confusion, since they did not know how to respond to this call, but within a year the First International Conference on Synthesis Reactors was called at Culham (Britain), and now the number of engineering studies in this area is increasing continuously. 458 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Budker was characterized not only by considerable scientific talent but also by organizational capacity. He clearly understood that the budget of the Academy could not possibly support the construction of all the sys- tems he conceived, but he clearly appreciated the scope for practical use of accelerators in industry. He de- cided to initiate the construction of electron accelerators providing several megaelectron volts but below the photonuclear reaction threshold, in which the extracted beam should be used for radiation technology, e.g., for modifying polymers, sterilizing grain, and the like. Although the design principles of such accelerators were already familiar, they had to be made reliable to industrial standards and capable of operating without spe- cialized staffs. He set up a large design office and production section to make accelerators for various users, and the facilities acquired by agreement in manufacturing the systems were then utilized in constructing the storage rings and the thermonuclear systems. Budker attached very considerable importance to staff training; he always devoted much effort to any talented young worker. He welcomed visiting scientists and engineers personally and always discussed their topics in detail. An outstanding innovation of his was the regular round-table meeting, which will be familiar to anyone who has worked at the Institute of Nuclear Physics. This table was of diameter 5 m and readily accommodated over 30 staff members. Budker made it a rule to meet at this table every day with a cup of coffee at 12 noon along with the leaders of the scientific teams, with the particular object of becoming ac- quainted with any scientific news arising during the day. Guest workers were also welcomed. New ideas were exchanged here in a free and easy setting, and these regular meetings played a large part in consolidat- ing the team, in which, as Budker constantly emphasized, there should be no internal rivalry on success of one at the expense of another. In this collaboration he saw the responsibility for the success of the Institute as a whole, since each of those gathered arcund the round table had considerable influence in the Institute and should support and extend this collaboration. He repeatedly said that the Institute is not a building or a set of hard- ware but a team that works in it in common. Budker is unfortunately no longer with us, but his team lives on, in its unique form and with its con- siderable potential. The team at the Institute included many who have since had to move to other institutes or to industry; however, after working in close contact with him, they intend to advance his scientific and engineering achievements. ARTICLES THE GYROCON, A HIGHLY EFFICIENT CONVERTER OF ENERGY FROM POWERFUL RELATIVISTIC BEAMS FOR MICROWAVE SUPPLIES IN CHARGED-PARTICLE ACCELERATORS G. I. Budker, M. M. Karliner, I. G. Makarov, S. N. Morozov, 0. A. Nezhevenko, G. N. Ostreiko, and I. A. Shekhtman UDC 621.385.6 The problem of high-power rf supplies for new accelerators continues to be of constant interest. As a solution to this problem, in 1967 G. I. Budker proposed a microwave oscillator which employed bending of a relativistic particle beam, the gyrocon* [1]. The design of the simplest version of a gyrocon is sketched in Fig. 1. A continuous electron beam (ray) from a high-voltage accelerator is deflected by the rotating magnetic field of the sweep resonator. This reso- nator is supplied by an exciter to which an input rf signal is fed. The deflected electrons move along straight lines which forth a conical surface and are located on it in the shape of a helical line whose end describes a circle. An electrostatic electrode system directs the electrons into an annular slit in the output resonator *Gyros (Greek) = circle+ continuum (Latin); referring to the circular deflection of a continuous (unbunched) beam. Translated from Atomnaya &lergiya, Vol. 44, No.5, pp. 397-403, May, 1978. Original article submitted December 25, 1977. 0038-531X/78/4405-0459807.50 ?1978 Plenum Publishing Corporation Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 459 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 2 3 4 an\ V 6 :?: I V/ 0 V/ I '' , , A A t==i Fig. 1 Fig. 2 Fig. 1. A sketch of a gyrocon: 1) high-voltage accelerator; 2) electron ray; 3) sweep resonator; 4) rf exciter; 5) electrostatic deflection sys- tem; 6) output resonator; 7) energy outlets; 8) collector; 9) compensat- ing electromagnet; a) the scan angle; dashed lines) static magnetic field lines. Fig. 2. The sweep resonator: H) magnetic field lines; E) electric field lines; 1, 2) power inputs; S) the direction of rotation of the field. which is tuned to the sweep frequency so that at resonance oscillations develop in it with a maximum electric field in the region of the annular slit through which the electron ray passes. The point at which this ray enters the resonator is continuously changing so the ray excites a traveling wave in the resonator. The electric field of the wave slows down the electrons and converts the power in the ray into microwave power. The remaining energy of the electrons is scattered in the collector. The circular sweep of the gyrocon beam is done by the magnetic field of a cylindrical resonator with E110 oscillations [21 (Fig. 2). The two power inputs for this resonator are supplied with a phase shift of 90? which ensures circular polarization of the magnetic field in the near-axial region where the electrons pass as they are being deflected. In the output resonator (see Fig. 1) the electrons excite a traveling electromagnetic field of the same configuration as in the sweep resonator, but the electrons pass through in an antinode of the electric field. The output resonator is essentially a rectangular waveguide with an H10 wave bent into a ring. This resonator is tuned to the sweep frequency, but can be tuned to a multiple of that frequency. In that case the gyrocon operates as a frequency multiplier. The two energy outlets are located azimuthally at 90? with respect to one another, similarly to the power inputs on the sweep resonator (see Fig. 2). When they are loaded equally and the reso- nator is excited by the electron beam, they ensure a traveling wave regime in the resonator. This regime can be maintained with a larger number of energy outlets as well [1]. The electrostatic deflection system is part of a spherical condenser. An electromagnet produces a static transverse magnetic field in the drift gap of the output resonator which compensatea the effect of the magnetic field of the traveling wave (which reduces the efficiency of slowing down the relativistic electrons). The gyrocon is free of the fundamental limits on electronic efficiency typical of high-power klystrons and microwave devices with grid control since in it there is no density modulation of the electron flow. In fact, the transverse dimensions of the high-power relativistic electron beam are much smaller than the wavelength of the traveling wave in the output resonator so all the ray electrons are slimed down almost identically. Thus, it is possible to obtain an electron efficiency in a gyrocon of close to 10070. 460 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 TABLE 1. Maximum Power from a Gyro- con uo, kV 4nax , MW uo, kV Pmax . MW 500 8 2000- 720 1000 70 3000 3000 1500 270 ' Density modulation of the electron flow did not occur in the first microwave devices with beam deflec- tion. One of these, a device with an annular traveling-wave resonator [3, 41, is a prototype gyrocon. How- ever, the lack of means to obtain a relativistic electron beam and to efficiently slow it down limits this device to low powers. In a gyrocon with relativistic electron energies it is possible to send a high-power electron beam through the apertures and slits of the resonators with a small current drop so that in it the forces of magnetostriction weaken the effect of the transverse space charge forces by y2 times (where y is the relative energy of the elec- trons). This makes it possible to achieve microwave powers with a gyrocon which could not be reached with the devices described in [3-8] which operate in principle at nonrelativistic electron energies. On going to relativistic energies in devices with an annular traveling wave resonator, the action of the magnetic field of the wave may significantly change the direction of motion of the electrons as they leave the resonator which has been excited by the beam. An electron directed along the lines of the slowing-down field gains a noticeable azimuthal velocity opposite to the direction of motion of the wave and that part of the energy associated with this velocity cannot be converted to energy of microwave oscillations. In this regard the elec- tron efficiency (tie]) of a device with an annular traveling wave resonator can be substantially less than 100% (1): ?13,;[:?(1iv2)1 1e1 ? V 1=-11) Et ? (1/v2)1 where go = VG/C is the reduced velocity of the electrons upon entering the resonator and v = Vic (V is the phase velocity of the traveling wave and c is the speed of light). For v = 1.84 (resonator 6 of Fig. 1) and go ? 1 the electron efficiency is 65%. In the gyrocon this drop in efficiency is eliminated with the aid of a static magnetic field which is either produced in the output resonator (the compensating magnet 9 of Fig. 1) or is located so the electron beam passes through it in advance. In the latter case, the angle at which the electron enters the output resonator of the gyrocon in order to obtain 100% efficiency is (1) 1-111--Tig 1p= arctg -11A721310, ? (1 ? (2) and for v = 1.84 and 130 ? 1 is no more than 33?. The first working model of a gyrocon was built according to the design of Fig. 1. In 1971 a power of more than 600 kW into a load was obtained from it with an electron energy of 320 keV in a pulse lasting 20 ?sec and it was experimentally confirmed that an electron efficiency of over 90% could be obtained at a frequency of 430 MHz. To illustrate the prospects for the gyrocon, we now evaluate its main parameters. For the calculations we shall assume that the transverse dimensions of the beam in the gyrocon do not exceed the dimensions of the free relativistic electron beam as it expands due to space charge forces [9]. We shall suppose that the elec- tron beam at the outlet from the accelerator has been focused optimally [10] and has sharply defined bound- aries. We shall consider only the azimuthal dimension of the beam cross section in the output resonator and assume that the other transverse dimension can be substantially reduced by means of focusing after the sweep. We shall assume furthermore that the deflection angle of the electron beam in the sweep resonator is small (5-20?) and that the transit gap of this resonator has been chosen so that the losses at the walls will be roughly equal to the losses due to accelerating electrons from the swept beam at its peak power and with a minimum excitation power. We also assume that the transit gap of the output resonator has been chosen sub- ject to the conditions for minimum electric field strength for complete slowing down of the electrons. 461 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Fig. 3 Fig. 4 Fig. 3. The layout of a radial gyrocon: 1) high-voltage accelerator; 2) elec- tron beam; 3) sweep resonator; 4) rf exciter; 5) magnetostatic deflection sys- tem; 6) output resonator; 7) collector; 8) energy outlets. Fig. 4: A sketch of a siveep ystein with a passive resonator: 1) electron beam; 2) high-voltage accelerator; 3) sweep resonator; 4) rf exciter; 5) pas- sive resonator; al and a are the sweep angles in the active and passive resonators (a/a1 10 for 1 An analysis of the operation of a gyroconwith these assumptions yields the following relationships for the principal parameters: Output power Electron efficiency Gain coefficient Minimum wavelength max = 4.10-5 (DI L)211,V2 [(el incz) (U012) + 113/2? ssin tscp/2 nD tg rh) n el Ay/2 yo ?1 r, =5.10-6 X Pmax Itmax c, V kai evo +11 ? X, min ,--- (1.6.109(?:-1)/Ernax. (3) (4) (5) (6) Here Pmax is the limiting beam power in the gyrocon, roughly equal to its output microwave power; n el is the ratio of the power converted into microwave oscillations to the beam power; Kmax is the ratio of the power converted into microwave oscillations to the exciter power for the sweep resonator at X; Amin is the working wavelength of the gyrocon;D and L are the initial diameter and length of the beam; U0 is the accelerating voltage of the electron source; e and m are the electron charge and mass; c is the speed of light (mcVe = 5.11 105 V), Act) is the azimuthal dimension of .the beam in the output resonator; yo = (eU0Anc2) + 1 is the ini- tial relative energy of the electrons; a is the deflection angle of the deflected beam; (5 is the thickness of the skin layer of the sweep resonator wall material; and Em ax is the allowable electric field strength in the out- put resonator. (The coefficients in these equations are for SI units.) Assuming that it is possible to draw high-power electron beams with D V20 and L 2X through open- ings in the resonator slits of the gyrocon, we find the maximum attainable gyrocon powers from Eq. (3) (see the table). Presently this power is limited by the capabilities of high-voltage accelerators whose steady state operating parameters correspond to the first column of the table and whose microsecond pulse operating re- gimes correspond to the third column. Evidently much higher powers are possible in the long term. 462 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Fig. 5. A cw gyrocon with a design power of 5000 kW. For electron beams with the parameters given in the table it is possible to obtain an azimuthal dimen- sion Ay9 -s- 30? for sweeping at an angle a?: 5.7? in the meter- and decimeter-wavelength range. Under these conditions tie]. 96% (4). The efficiency of a gyrocon is limited in principle by the following factors: the finite transverse dimension of the beam in the output resonator and the resulting nonidentical slowing-down conditions for the electrons; the scatter in energy of the beam electrons due to the circular sweep; and, the incomplete slowing down of the electrons since they must be removed to the collector. Equation (4) takes only the first two factors into account. An analysis shows that the scatter in the energy during the sweep makes it possible to neglect the effect of the third factor. There are other reasons for a reduction in the efficiency such as the initial scatter in the energy of the electrons, instability in the beam current, imprecise choice of load on the output resonator, and so on, whose effect may be eliminated by a reasonable choice of the parameters of the stabilizing systems and allowances for the structural elements of the gyrocon. An exception must be made for two such factors whose effect is difficult to remove in a gyrocon: for losses of beam current the level of which we shall assume can reach 1%, and for differences between the wave in the output resonator and the travelling wave. The latter is charac- terized by the ratio of the maximum and minimum values of the amplitude of the voltage on the transit gap of the output resonator around the annular slit. Assuming that this ratio can be held to a level of 1.03, we then assume a further loss in the efficiency of the gyrocon by 1.5%. The overall efficiency of the gyrocon is reduced by losses at the walls of the output resonator (2%), as well as by losses in the electronic, vacuum, and other equipment in the gyrocon (3%). A further 5% can be due to losses in the stabilization system for the energy of the high-voltage electron accelerator. These estimates are for maximum power from a cw gyrocon in the meter-wavelength range (U0= 500 kV). As the accelerating voltage is increased (U0 1000 kV) the first two loss mechanisms may be neglected. Thus, the limiting values of the electron efficiency (90-95%) and overall efficiency (85-90%) provide an idea of the energy performance of the gyrocon. For gyrocons with the parameters listed in the table the gain coefficient (5) is Kmax = 100-3000 (20-35 dB) for tana = 0.1. However, such a small sweep angle can be achieved in the simplest design (see Fig. 1) only 463 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Fig. 6. A pulsed gyrocon with a design power of 200 MW. by elongating the beam, that is, by reducing the peak power. The gain coefficient can be increased without re- ducing the power by further bending the beam with a static field which does not require expenditure of rf power. An alternate gyrocon design in which this approach is used with a minimum beam length is shown in Fig. 3 [11]. The additional deflecting system shifts the weakly deflected beam into a plane perpendicular to the axis of the gyrocon. In this variant the output resonator is a rectangular waveguide with an H10 wave bent into a ring in the E plane (and not in the H plane as in Fig. 1). The system that deflects the relativistic beam by almost 90? (see Fig. 3) is a magnetostatic system (e.g., in the form of a conical coil) since an electrostatic system does not have the required electrical breakdown strength. As it moves in the radial magnetic field near the apex of the conical coil an electron describes a tra- jectory with a double curvature. It not only moves into a plane perpendicular to the axis of the gyrocon, but also acquires an azimuthal velocity component needed for getting into the output resonator at a given angle 0(2). The maximum magnetic induction in the deflection system does not exceed a few Tesla (for a gyrocon in the decimeter range with tan? = 0.1 and U0 = 3000 kV). The azimuthal defocusing of the beam in such a sys- tem does not cause its size to exceed Acp = 30?. Thus, a gain coefficient of 20-35 dB can be obtained in a radial gyrocon with L',"=1 2A., that is, without re- ducing the maximum power and electrical efficiency mentioned above. The gain coefficient can be increased further by using a sweep with a passive resonator (Fig. 4) [12]. In such a device the sweep resonator is followed by a passive resonator which is identical to the sweep resonator but has no power inlets. The electron beam, blown up to a small angle by the field in the sweep resonator, excites a traveling wave in the passive resonator which further deflects the electrons. Part of the beam power is then lost to rf heating of the walls of the passive resonator. An analysis of the operation of such a system demonstrates the possibility in principle of increasing the gain coefficient of a gyrocon by a factor of 100 al- though this involves some reduction in power. The formula for the minimum working wavelength of a gyrocon (6) takes into account the limitation due to the insufficient breakdown strength of the transit gap of the output resonator. For cw operation of the reso- nators Emax 5-10 MV/m is permitted, while for microsecondpulseoperation Emax -5 50 MV/m is possible. Under these conditions and at the power levels listed in the table 0.3 -5 Amin 5 1.1 m for cw operation and 0.06 5 Amin -5 0.22 m for pulsed operation. At wavelengths smaller than 0.1 m, however, the initial assumptions about the attainability of current deposition on the walls of less than 1% and small beam diameters (D N/20) at powers of tens and hundreds of megawatts may not be satisfied. This may place significant limitations on the efficiency and power of the gyrocon. In this frequency range (108_109 Hz)the Q-factor of the sweep resonator is of order 104. The narrow fre- quency bandwidth associated with this Q evidently limits the use of the gyrocon in information transmission systems. Any expansion of this bandwidth involves a corresponding reduction in the gain coefficient. These calculations of the basic parameters show that in the meter- and decimeter-wavelength range the gyrocon is capable in principle of developing rf powers considerably higher than that of klystrons [7] and tubes 464 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 with grid control [8], with .a gain coefficient of greater than 40 dB, with an unusually high electron effi- ciency (90-95%) for microwave devices. Realization of these parameters requires solution of a number of complicated technical problems which appear both in the development of any kind of very high power microwave devices and uniquely in the develop- ment of gyrocons. The latter problems include the construction of an electronic and optical circuit for the gyrocon such that the current deposition on the walls is less than 1% when the electron current cannot be tracked by a constant magnetic field. This problem involves building an rf system which maintains the high accuracy of the circular polarization of the magnetic field in the sweep resonator and constructing a system for stabilizing the energy of the electrons which come in from the high-voltage accelerator. Highly efficient operation requires a system for precisely maintaining the traveling wave regime in the output resonator. This listing of problems shows that construction of a complicated device such as the gyrocon is justified only for such values of the main parameters as cannot be obtained with the aid of simpler microwave sources. Electron-beam microwave devices similar to gyrocons but without their performance characteristics have been described in the literature several times [3-6]. The new components needed for high power, effi- ciency, and gain levels and which distinguish the gyrocon from these other devices are the following: ? a relativistic electron source; ? a compensating electromagnet or magnetic system for directing the electrons into the output resonator at a given angle which makes it possible to completely stop the relativistic electrons; and ? a magnetostatic deflection system which permits operation with a small sweep angle and a minimum beam length, as is necessary for high gain at high powers. At the Institute of Nuclear Physics (Novosibirsk) two gyrocons have been built at the initiative of G. I. Budker. They have the following design characteristics. 1. a cw gyrocon for the rf supply of the resonators on the VEPP-4 electron?positron storage device: Output power . 5000 kW Accelerating voltage . 500 kV Working wavelength .. 1.65 m Gain coefficient 23 dB Overall efficiency sa 2. A pulsed gyrocon for the rf supply for the linear accelerator in the positron source for the VEPP-4: Pulsed power 200 MW Accelerating voltage 2000 kV Pulse length .. 10 ?sec Repetition rate 1 Hz Working wavelength . 0.7 m Gain coefficient . ? .. 25 dB The first sets of bench tests have been made on these devices. In the cw gyrocon (Fig. 5) [13] an electron beam with a power of more than 1000kW has been obtained, swept with a frequency of 181 MHz, and passed through a detuned output resonator. The electron energy in this experiment was 220 key. A 700-kW electron beam (with an electron energy of 210 keV) excited the output resonator of the gyrocon and the cw rf power was 500 kW. The goal of the tests is to develop the electronic and optical circuit of the gyrocon. The current deposition in these experiments was less than 1%. The pulsed gyrocon (Fig. 6) [14] developed a pulsed power of 40 MW at 430 MHz with a pulse length (at the half power points) of 6?sec and a repetition rate of 0.5 Hz (the electron energy is 1300 keV). A gain coef- ficient of 23 dB was achieved. The purpose of these tests is to develop a scheme for producing positrons with a linear accelerator driven by the gyrocon. The results obtained previously in tests with a pulsed gyrocon where an electron efficiency of over 90% was measured and the experimental data given here confirm the validity of our ideas on the performance of the gyrocon. The data show that this new microwave source can find application in accelerator and microwave 465 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 power technology, especially in those areas which require high power in a single piece of equipment with mini- mal losses. LITERATURE CITED 1. G. Budker et al., US. Patent No.3885193 (May 1975); U. K. Patent No.1433236 (August 1976); Swiss Patent No. 562533 (May 1975). 2. M. M. Karliner et al., "A device for circularly sweeping a beam of charged particles," Inventor's Certi- ficate No. 471847 (1975). 3. A. Whall and J. Pickin, U.K. Patent No. 954840 (June 1974). 4. I. Kaufman, U.S. Patent No. 3219873 (Nov. 1965). 5. P. Harfley, U.S. Patent No. 2381539 (Oct. 1945). 6. I. McRae, U.S. Patent 2408437 (Oct. 1946). 7. G. Konrad, IEEE Trans. Nuclear Sci., NS-22, 1249 (1975). 8. L. Clampitt (editor), High-Power Vacuum Electronic Microwave Devices [Russian translation], Mir, Moscow (1974), pp.50, 126. 9. I. N. Meshkov and B. V. Chirikov, Zh. Tekh. Fiz., 35, 2202 (1965). 10. V. Kleen, Introduction to Microwave Electronics [in Russian], Sovet-skoe Radio, Moscow (1963), p.443. 11. G. Budker et al., U.S. Patent No. 4019088 (April 1977). 12. M. M. Karliner et al., "Gyrocon," Inventor's Certificate No. 503444 (1975). 13. G. I. Budker, in: Proceedings of the Fourth All-Union Conference on Charged Particle Accelerators [in Russian], Vol. I, Nauka, Moscow (1977), p.284. 14. G. I. Budker, ibid., p.280. INDUSTRIAL ELECTRON ACCELERATORS DESIGNED AT THE INSTITUTE OF NUCLEAR PHYSICS, SIBERIAN BRANCH, ACADEMY OF SCIENCES_ OF THE USSR V. L. Auslender and R. A. Salimov UDC 621.384.6 Budker [1] initiated work on electron accelerators for industrial purposes at the Institute of Nuclear Physics; until recently, this work was done under his direct supervision. The work had attained a large scale by 1966, and up to the end of 1977 the Institute had built and supplied over 45 accelerators. Electron accelerators are used in many processes in radiation chemistry, in particular for irradiating polyethylene insulators, producing thermally shrinkable components, and killing insects in grain. No radio- isotopes are produced on irradiation with electron beams of energy up to 2 MeV, while the dose rates are larger by many orders of magnitude than those available from radioisotope sources. An electron accelerator producing a current of 1 mA is roughly equivalent to a radioactive source of 105 Ci. There is no residual radio- activity, while the dose rate is high, and the shielding is comparatively simple, so electron accelerators are widely used in industry where substantial throughputs are required. For instance, a dose of 1 Mrad may be required with 60% use of the electron beam (one-sided irradiation of sheet materials or liquids), in which case an accelerator providing an output beam power of 20 kW can provide a throughput of 4 tons/h. Various beam-extraction systems are used, which provide radiation fields of various shapes; several types of accelerator had been designed previously in the USSR [2, 3] for use in radiation chemistry, but the electron energies of these did not exceed 1 MeV, while the output at a single point did not exceed 10 kW, which restricted usage considerably. Here we survey researches at the Institute of Nuclear Physics on the design of electron accelerators for industrial purposes, as well as major uses. Translated from Atomnaya nergiya, Vol. 44, No.5, pp. 403-408, May, 1978. Original article submitted January 16, 1978. 466 0038-531X/78/4405-0466507.50 @1978 Plenum Publishing Corporation Declassified and Approved For Release 2013/03/07: CIA-RDP-10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Fig. 1. General view of the ILU-6. The Institute has designed the fLV and ILU* accelerator models, whose mean power output is consider- ably in excess of 10kW at energies from 400 to 2000 keV, and which are intended for direct use in industrial processes. In addition, other accelerators of types ELIT and ESU have been designed, which are used for other purposes. The ILU-6. This is a pulsed high-frequency accelerator used as a high-power radiation source. The accelerator uses a toroidal cavity working at 100-127 MHz. The self-excited oscillator is mounted directly on the cavity; this uses a common-grid circuit. The accelerator gap determines the working frequency and the limiting energy, and this can be adjusted from 10 to 20 cm. If a 20-cm gap is used, the resonance fre- quency is 127.5 MHz, the quality factor is 2 ? 104, and the shunt resistance is 4- 106 Q. The cavity is contained in a steel vacuum chamber, which is evacuated by four magnetic-discharge pumps type NORD-250. All the main vacuum seals are made of indium. The working pressure is 10-6-10-7 mm Hg. The electron beam is separated from the accelerating gap by a grid, which means that a bias can be ap- plied to the cathode to regulate the current. The cathode cannot be mounted directly in the gap because the electrons entering the gap after a certain phase in the accelerating half-wave do not have time to pass across the gap and therefore return and may cause considerable damage to the cathode. This means that it is diffi- cult to maintain a constant power output in the electron beam as the accelerating voltage is reduced. Constant power may be maintained throughout the working energy range (0.4-2 MeV) by increasing the pulse repetition frequency from 50 to 300 Hz while maintaining the same mean power input to the oscillator tube, while on the other hand the gap can be reduced from 20 to 7-10 cm. Both methods allow one to use the same accelerator design to produce a fixed mean power over a reasonably wide energy range. There is a short magnetic lens immediately after the plate hole, which allows for on-line correction of the transverse beam direction at the exit. *The following participated in the design of the ILU: V. L. Auslender, G. B. Glagolev, G. I. Kuznetsov, N. A. Livshits, R. M. Lapik, V. A. Polyakov, A. D. 13anfilov, A. A. Tuvik, V. G. Chesnokov, and I. L. Chertok; and the following participated in the design of the ELV: A. A. Avdienko, V. A. Gaponov, B. M. Korabeltnikov, G. S. Krainov, S. A. Kuznetsov, N. K. Kuksanov, V. I. Kondrat'ev, R. A. Salimov, V. G. Cherepkov, and A. I. Sha- rapa. 467 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Od A-A Com- pressed air Fig. 2. Design of the ELV-3: 1) vacuum pump; 2) high-voltage electrode; 3) case; 4) conical magnet; 5) primary winding; 6) cylindrical magnet; 7, 10) rectifier sections; 8) control unit; 9) accelerator tube; 11) disk magnet; 12) output section. The ILU-6 is a fairly compact system (Fig. 1) whose major parameters are as follows: Electron-energy range, keV 400-2000 Electron beam power at all energies, kW 20 (30-35 kW under certain conditions) Energy spread in beam, %. t10 Pulse length, ?sec up to 700 Pulse repetition frequency, Hz. up to 300 Power supply, line frequency, V. 3 x 380 Power drawn, kW up to 100 The ELV accelerators [4] have the accelerating voltage provided by a rectifier whose design was initiated in the Institute in 1971; in 1974, the Interdepartmental Commission accepted the ELV-1, while the fLV-2 was accepted in 1975. Both of these have passed reliability tests over several thousand hours running and have been recommended for routine industrial use. The working principles of the LV-1 have been described in de- tail elsewhere [4], and here we merely describe the differences in the subsequent models. The following are the parameters of these accelerators: 468 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 fiv-i fLV-2 ELV-3 ELV-4 Electron energy range, keV 400-1000 800-1500 400-700 800-1500 Electron beam power throughout energy range, kW 20 20 50 40 Ripple on accelerator voltage under load, % 2.5 2.5 2.5 2.5 Total dissipation in accelerator at maximum output, kW 3.5 4 5 5 Size of accelerator without output section, m: height 2.8 2.8 2.8 2.8 width 1.6 1.6 1.6 1.6 The increased output of the ELV-2 (by comparison with the ELV-i) has been attained by increasing the number of rectifying sections from 24 to 37 and extending the accelerator tube from 1200 to 1500mm; the beam power in these first two models was restricted not only b3i the acceptable ripple at the filter capacitors (re- striction on the rectified current) but also by the load characteristics of the high-voltage transformer. Sub- sequent developments have shown that the existing dimensions can be retained while the capacitance can be doubled in each section. The power restriction imposed by the high-voltage transformer is seen as a nonuni- form voltage distribution over the secondary winding, since the diameter of the latter is comparable with the height of the primary winding. This effect has been eliminated in the fLV-4 by using a variable winding pitch for the primary. This design allows the rectifier to operate with loads up to 20 ma with the maximum voltages on the sections exceeding the mean by only 10%. An electron-beam power of 75 kW has been attained in short- term running with the ELV-4. Longer-term tests (over 100 h) have been performed at 40 kW. The ELV-3 differs in design from the other accelerators (Fig. 2); here the two rectifiers are assembled in a common case and have a common magnetic system, and they work in parallel into a single accelerator tube. The upper and lower ends of the rectifier column are at ground potential, while the middle is at the high potential. The distribution of the magnetic flux is symmetrical on account of the disk systems used at the ends, so there is no nonuniformity in the voltage distribution over the secondary. The ELV-3 can work into a load of 3 MSZ. The accelerator has been tested at an output of 50 kW for over 100 h. All the ELV series accelerators have high immunity to damage from the overvoltages that may arise from breakdown in the gas or vacuum insulation, which is a very considerable advance over existing Soviet accelerators. The major elements have been maximally standardized for the various styles of accelerator; e.g., there have been virtually no changes in the size of the pressure vessel, vacuum system, or the control circuits, or in the measuring and gas-handling systems. Pulsed and High-Power Electron Accelerators. The ILU and ELV are in direct industrial use, while the Institute has also developed the pulsed ELIT [6] and the high-power ESU [7]. The parameters of the ELIT are given below. , ELIT-0.8A ELIT-1B ELIT-2 Mean electron energy in pulse, MeV 0.8 1.1 1.5 Mean beam power, kW 0.8 4.5 10 Energy spread in beam, % 10 10 15 Pulse length, ?sec 1 2.5 3.5 Pulse power, MW . 8 20 30 Window size (transmission through foil), mm 153x35 420x65 420x65 Input voltage to rectifier, kV 20 10 10 Line power drawn, kW ? ? ?? 3 20 40 Dimensions of accelerator without output section, m: height 0.76 1.15 1.92 diameter 0.4 1.0 1.0 The ELIT-2 has means of outputting a focused beam into the atmosphere; this has operated stably during long-term tests. The ESU accelerators have been designed to provide outputs in the megawatt range; the following are the design parameters of the ESU-2: 469 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Fig. 3. Device for irradiating cylindrical components: 1) beam; 2) scan system; 3) tube; 4) foil; 5) specimen; 6) magnet; 7) winding. Electron energy range, keV 30-500 Electron current, A up to 10 Ripple on accelerating voltage, % ?2.5 Working mode continuous Dimensions of rectifier, m: height 3.5 diameter 2 Dimensions of accelerator tube with power and control unit, m: height ..... ? . 4 diameter 1.2 The ESU-1 is intended only for short-term operation; it can operate with an evacuated target for 10 sec to provide a power of 1100 kW at 250 keV. An air beam providing a power of 400 kW has also been extracted with this accelerator [6]. The ESU-2 is currently in use for testing the gyrocon high-frequency generator [9]; this has yielded a power of 1000 MW, but in this instance in continuous mode. Beam Outlet Device. The ILU and ELV are equipped with various devices for outputting the electron beam into the atmosphere. The simplest device is one employing output of a linearly expanded beam through a titanium foil cooled by air. This can handle up to 0.15 mA/cm2. The working life of the foil exceeds 1000h. The standard exit window is 75 x 980 mm and can handle currents up to 80 mA. The beam deflection angle is 30?. Each current pulse is uniformly distributed over the foil in the MU. A sawtooth scan of the beam along and across the window is used in the ELV. The transverse scanning frequency is 1075 Hz, while the longi- tudinal frequency is usually 50 Hz, but this can be raised to 400 Hz if there is some special requirement. The nonuniformity in the dose distribution along the window received by a component moving transverse to the window is not more than ?103. The 500-keV electrons passing through the foil are scattered through about 45?, but this angle decreases linearly as the electron energy increases. Cylinders (tubes and the like) may be irradiated with two types of device employing a ring scan; Fig. 3 shows a device of the first type. The beam emerges through a standard window and is directed by permanent magnets onto the cylindrical workpiece. This device has been tested at electron energies from 800 to 1500 keV with the ELV-2. The proportion of the current reaching the workpiece is 70% for a tube of diameter 6cm or or 50% at 4 cm, while the deviation from uniformity of the current distribution in azimuth at the tube is not more than ?10%. The same system has been used to irradiate three tubes of diameter 2 cm simultaneously. These receive 50% of the accelerator current. The deviation frojn uniformity is also not more than ?10%. The system can handle tubes up to 15 cm in diameter. The ILU and ELV can be fitted with similar devices. 470 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Fig. 4. General view of output section in ILU accelerator. Another type of annular system can be used only with the ILU, since the pulsed operation allows one to deflect each pulse into a distinct channel and then direct it by means of magnets onto window foils. This means that a three-dimensional radiation field can be set up with a nonuniformity of not more than ?15% and with less loss. Figure 4 gives a general view of the device. An output beam is also obtained in a device in which the beam escapes from the vacuum via a system of four holes [5]; the fall in pressure from atmospheric to 10-6 mm Hg in the accelerator tube is provided by five pumping stages, of which the last (magnetic-discharge pumps) is used with the accelerator in any mode of beam output. The parameters of the ELV beam are such that a hole of diameter 1 mm will transmit 20 kW with a di- vergence of 5.10-2 rad. An output of 75 kW is available from a hole of size about 1.5 mm. The total power dissipated on all stops is not more than 3 kW. Industrial Uses. Various processes in radiation technology have already been based on these accelerators built at the Institute of Nuclear Physics, Siberian Branch, Academy of Sciences of the USSR. Irradiation of polyethylene components is the most common use. Crosslinking gives improved chemical resistance to poly- ethylene, as well as mechanical strength and thermal stability, which means that components,e.g., tubes, in- sulated wires, and the like, can work for long periods at 135?C and for short periods up to 250?C. Nine industrial lines have been built by the Ministry of the Electrical Engineering Industry to produce wires and cables with heat-resistant polyethylene insulation by means of ELV accelerators. The ILU has been used in a system for producing heat-resistant polyethylene tubes for hot-water supply; 1 ton of these tubes saves 5 tons of metal tube. The economic gain from using a single line based on an ILU is given by the Kharpov Institute of Physicochemical Research as more than 1 million rubles per year. A further use of irradiation is to produce shrinkable tubes based on polyethylene and fluorinated polymers. Processing lines with ILU-6 accelerators for the purpose are being built by the Plastik organization in Moscow and by the Plastpolymer organization in Leningrad. Also, equipment being designed for producing regenerated butyl rubber from worn components and for radiation purification of industrial effluents containing large amounts of surfactants. The ELV beams provide high energy densities; e.g., a beam power of 60 kW corresponds to a heat-flux density at the surface of the target under vacuum of 2- 106 W/cm2. The flux density at the surface of a target in helium at atmospheric pressure at 3-5 cm from the output device is 5 ? 105 Wicm2. These beam features mean that the beams can be used in electron-beam technology under vacuum or in gases. Preliminary tests show that the ELV-4 gives good performance in cutting and welding metals. 471 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Accelerators have also Many uses in agriculture; the ELV has been used in killing insects in grain, and ?experimental system at Novosibirsk Branch of the All-Union Grain Research Institute has been used in pro- cessing about 1200 tons of grain. The tests proved very favorable, and a prototype industrial system of through- put 200 tons/h was built in 1978. The ccinstructimi of large pig-breeding stations (miek 106,000 pigs each) has raised problems in pto- cessingeffluents;in1978;anILU-6 was built into a prototype system for processing effluents with a throughptit of 1000-2000 m3/day. LITERATURE. CITED I. G. I. Budker, in: Proceedings of the Second All-Union Conference on Industrial Uses of Charged-Particle Accelerators [in Russian], Izd.NIIEFA, Leningrad, vol.. 1, 48 (1976). 2. 0. A. Gusev, ibid, Vol. 1, p. 265. 3. B. P. Murin et al., ibid., Vol. 1, p.265. 4. G. I. Budker et al., Atom. Energ., 40, No.3, 216 (1976). 5. G. I. Budker et al., in: Proceedings of the All-Union Conference on the Design and Use of Electron Accelerators [in Russian], Tomsk (1975), p.188. 6. S. B. Vasserman et al., Proceedings of the Fourth All-Union Conference on Charged-Particle Accelera- tors [in Russian], Nauka, Moscow (1974). 7. V. A. Gaponov et al., in: Proceedings of the All-Union Conference on the Design and Use of Electron Accelerators [in Russian], Tomsk (1975), p. 131. 8. V. M. Ievlev et al., Izv. Akad. SSSR, Nauk, Sib. Otd. Ser. Tekh., No. 13, Issue 3, 52 (1977). 9. G. I. Budker et al., in: Proceedings of the Fifth All-Union Conference on Charged-Particle Accelerators [in Russian], Vol. 1, Nauka, Moscow (1977), p.284. GAS POROSITY ARISING ON ANNEALING IRRADIATED BERYLLIUM E. Ya. Mikhlin and V. F. Chkuaseli UDC 621.039.548 Neutron irradiation produces helium in beryllium; the solubility of the gas in the metal is negligible. Gas swelling then occurs if the temperature is high enough. It has proved extremely difficult to elucidate the behavior of materials of complex structure, since many processes act together. On existing views [1, 2], gas porosity is produced in the main by the displacement and fusion of pores. The rates of these processes are controlled by various factors, in particular the mechanism responsible for pore motion, the number of struc- tural defects whose interactions affect pore mobility, and soon. Model calculations have to be compared with the available experimental evidence in order to elucidate how far these general concepts apply to gas swelling in beryllium. To avoid complicating the model, we consider only the fusion of pores due to Brownian motion; the exter- nal forces acting on the pores and the interactions with other defects are neglected. Naturally, the results are to be compared with the porosity observed in some small region free from all other types of defect. Cor- respondingly, the dimensions of such pores must also be small. Little evidence is available on the initial stages of the growth of gas porosity in beryllium; an electron micrograph has been published [3] of the porosity observed in single-crystal beryllium irradiated in the SM-2 reactor with a fluence of 2.6.1021 neutrons/cm2 (E 0.8 MeV) at 60?C, which was followed by stepwise anneal- ing over the range 100-800C (temperature raised 50?C per hour). Although this photomicrograph does not meet the requirements fully (some of the pores appear to occur at dislocations), it may be compared with our calcula- tions. The dislocations restrict the mobility of only a small proportion of the pores visible in the photomicro- graph, so one assumes that the interaction with dislocations does not greatly retard the growth of the porosity, at least in the initial period. The comparison with experiment must show whether this assumption is correct. Translated from Atomnaya Energiya, Vol. 44, No. 5, pp. 409-411, May, 1978. Original article submitted April 23-, 1976. 472 6038-531X/78/4405-0472 $07.50 ? 1978 Plenum Publishing Corporation Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 f 1023- 50 100 150 200 250 r(A) Fig. 1. Size distribution f(r) in cm-4 (f(r)dr is the number of pores of radius from r to r + dr in cm3): 1) observed (from photomi- crograph [3]); 2-5) calculated for bulk diffu- sion; 2, 3) calculation with DT = 0.19 exp (-38.6/RT) (first series); 4, 5) calculated for DT = 0.7 exp (-50/RT) (second series); 2, 4) C = 0.75-102? atom He/cm2; 3, 5) C = 0.25- 1020 atom He/cm3; 6) calculation on 30-min annealing for surface diffusion. The calculations on the kinetics of collision and fusion for randomly wandering gas bubbles were based on the following concepts.* We assume that the gas in the pores is not ideal, while the pressure is balanced by surface-tension forces. There is then the following relationship between the radius ri of pore size i ( a pore of size i contains i times as much gas as a pore of the first size): / 4n r ??irnb = imkT ri 3 ( 1 ) Here y is the surface tension, b is the van der Waals constant, and m is the number of gas atoms in a pore of the first size. It is assumed that the pores grow only as a result of fusion occurringoncollisionbyBrownian motion. Any pore containing two or more gas atoms is considered as stable with respect to gas loss.t Then the time course of the pore concentration for size i, viz., Fi, is described by where !!L4n 2 FJ(t) F r DJ, 431 2 F, F, r?D?(-t+60), dt i=1 j=1 j=_-{i/2 for even i t?i ?2 for odd i. (2) The first sum on the right describes the increase in Fi due to fusion of pores whose size is less than i, while a second describes the fall in Fi due to fusion of pores of size i with pores of other sizes. Here rij = ri + rj and Dii = D + Dj are the sums of the radii and of the diffusion coefficients, respec- tively, for pores of sizes i and j; the equations have been solved by finite-difference methods. The porosity observed in [3] developed on annealing beryllium saturated with helium, so the model calculation was based on a state corresponding to a solid solution of helium atoms. This was characterized as a distribution of pores identical in size each containing one gas atom (pores of the first size). Therefore, Fi(0) = COii, where C is the initial concentration of the dissolved gas. The calculations on the porosity employed various concepts of the mechanism of pore displacement; if this is due to surface diffusion, the diffusion coefficient for the pores [4] is *See [4] for details. trhis corresponds to homogeneous. 473 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 A =-& (".) e (3) Here Dso is th9 observed surface-diffusion coefficient, y is surface tension, II is the volume per atom in the lattice, a = S21/3, r is pore radius, k is Boltzmann's constant, and T is absolute temperature. The diffusion coefficient for the pores responsible for the bulk diffusion is ? 7 ?3 j\3 '-'b ?7.D (r 9 . (4) where Dv is the bulk self-diffusion coefficient. In the surface-tension case, a calculation representing annealing for only 30 min at 800?C gives a poros- ity far greater than that actually observed (curve 6 of Fig.1 as compared with curve 1), particularly as the observations relate to prolonged stepwise annealing up to 8000C.* A calculation that would reproduce the experiment completely should result in even greater enlargement of the pores; therefore, the porosity observed after stepwise annealing [3] can hardly be explained in terms of surface diffusion in its simple form (without introducing additional factors, in particular retardation by struc- tural defects). Two series of calculations were performed for bulk diffusion, in both cases simulating stepwise anneal- ing [3); these involved two different assumptions about the parameters that determine the temperature depen- dence of the self diffusion: ?Q (5) D (T)= Do eRT . One series was based on values derived from experiment: Do = 0.19 cm2- sec-1 and Q - 38.6 kcal/g-atom [6]. However, the latter quantity is in poor agreement with the empirical relationship between Q in cal/g-atom and 32Tmp, which expresses the activation energy in terms of the melting point, and which is known to apply for a large number of elements [6]. Therefore, the second series was based on Q = 50 kcal/g-atom, which fol- lows also from the empirical relationship and the value Do =--0;7 cm2- sec-1 derived by calculation [6]. The values of a and y were taken as in the calculation orrsurface diffusion; in [31 we find no data on the aniount of gas formed in the specimen on irradiation in a fluence of 2.6..1021 neutrons/cm2 (E > 0.8 MeV), so we performed two calculations in each series. In one of them we assumed that C = 0.25- 1020 cm-3, and in the - -other that C = 0.75- 1020 cm3, estimates showed that the initial gas concentration must have fallen within these limits. Curves 2-5 of Fig. 1 show the calculated distributions; curves 2 and 3 (series 1) go with curves 4 and 5 (series 2) to show that a threefold change in the initial concentration results in a relatively small change in the size distribution. The comparison with the photomicrograph shows that the theoretical distributions in both cases are fairly close to the observed one (i.e., curve 1). As only approximate values are available for some of the parameters used in the calculations, while the model incorporates only fusion and neglects interaction with structural defects, we consider that the agree- ment with experiment is reasonably good. This indicates the main mechanism for gas porosity is fusion of randomly wandering pores in this partic- - ular case. LITERATURE CITED 1. R. Barnes, J. Nucl. Mater., 11, 135 (1964). 2. V. Agranovich, E. Mikhlin, and L. Semenov, in: Proceedings of the Third International Conference, Geneva, Vol. 11 (1965), p. 162. *The following values were used here: b = 4. 1023 cm3; 2 = 8.4 -10-24 cm3; C = 0.75.102? cm-3; t = 1 h; Dso = 10-6 cm2- sec-1 (this value was found from the observed curve relating logDso to Trimp, which itself was con- structed from the available data on surface diffusion in various elements [5] and y = 1700 erg/cm2 (this value was derived by extrapolation from y = 1200 erg/cm2 near Trap [6] on the basis of the y(T) applicable to copper). 474 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 3. G. A. Seriyaev, V. P. Gol'tsev, and E. I. Chechetkina, Preprint NIIAR, P-223, Dimitrovgrad (1974). 4. E. Mikhlin and Chkuaseli,Phys. State Solid., 29, 331 (1975). 5. N. Gjostein, in: Surfaces and Interfaces: Chemical and Physical Characteristics, J. Burke, N. Read, and V. Weiss (editors), Syracuse Univ. Press (1967). 6. I. I. Papirov and G. F. Tikhinskii, Physical Metallography of Beryllium [in Russian], Atomizdat, Moscow (1968). THE EFFECT OF A HORIZONTAL SHIFT OF THE REGULATOR E. A. Garusov UDC 621.039.562.2 The layers of construction materials or coolant surrounding an absorbing unit, fuel element, or regula- tor can exert a significant effect on the logarithmic derivative of the neutron flux at the surface [1]. It often turns out that the absorbing unit is positioned eccentrically with respect to the guide channel in which it is located. The motion of the coolant in the channel can cause vibrations of the unit, resulting in a redistribu- tion of the thickness of the gap occupied by the coolant, and thereby in a change of the effective boundary con- ditions. This situation is one of the causes of variation in the reactivity of a reactor (the appearance of "neu- tron noise"). A number of such causes have been discussed in detail in [2-41. In this paper the variation of the reactivity of a reactor is derived in the one-group diffusion approxima- tion as a function of the eccentricity of the axis of the "black" absorbing unit (the regulator) with respect to the axis of the guide channel. Let an infinitely long coolant channel of radius Ri with a regulator of effective radius R2 be placed in the active zone of a reactor with uniformly distributed neutron sources at its position. Let us assume that the conditions of applicability of the diffusion approximation are satisfied for the active zone (i = 1) and the gap with coolant (i = 2): Eai > Es-12. Since a decrease of neutrons in this region is deter- mined mainly by their leakage into the regulator, it is possible to neglect absorption in the surrounding medium by setting Eai = 0 when formulating the effective boundary conditions (and only in this case). The neutron source is assumed to be located at infinity (r. .0)-[5]. We will discuss within the framework of perturbation theory the variation 6k/k of the reactivity of the reactor caused by a small shift in the regulator axis by an amount 1>?a. z +11 (24a) (24b) Here r" and r' are the distances of an arbitrary point (x, y) from the two poles tc; 0 and 0" are the angles be- tween the radius vectors r' and r" and the abscissa. The coordinates of the poles are selected in such a way that the ratios irl /IV] of the absolute values of the vectors remain constant as their ends revolve around the circles T2 and Tt. It follows from this fact that and the equations yield the values d1,2: c2=41,2--71.2, (25) ?71 T2 Ti At RI? RI? Al. = 2ARI RI (RI+ A") ?(RI ? A2)2; MR/ (RI?A") ? (26) (27a) (27b) The coordinates of the points of the circles in bipolar system (1,2), which are related to their radii T1,2 by the relationship [9, 10] sh s I are constant and equal to t'. I _ 1 in d2, -I- e 1 1., lit (RI ? 6,2)? (RI? A") + 2 2 d2, 1?c 2 " RI (RI + /12)?(RI? A2) ? + (RI ? A") 1/(R/ ?RI)11-1- A4-26,3 (lit+ ?(14 ? A2)11 (RI? + A? 2A' (RI +RI) = ni; The source is situated at the point 2)0= 0. The system of Eqs. (20) along with the boundary conditions (21) will take the form , ( 0" 2872,2 ) (Di a, 506(1.-1.) 8 (11) A DI (ti, = ?I); Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 (28) (29) (30) (31) (31a) 479 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 ?O 11) It_ta D2na 11) a`Di g' =0; 0.2 (t2, n)=0 (31b) (31c, d) in bipolar coordinates (Fig. 3). Since the problem possesses symmetry with respect to /1, the finite Fourier cosine transform [12) can be used for its solution: m) (t, n) cps inn m 0 , 1 . Then the solution will have the form CO 01(, n)=(Di 0)+1- 2 cos mv:Di g m) n ' m=t (32): (3p) Applying (32) to system (30)-(31), finding 6ig, m) and substituting them into, (33), we obtain expressions for the neutron fluxes in the active zone (4)1) and in the gap (4)0 where f Di cos M Ds (Di (1 = 2?D, k (to).+ (ta--4)-1- 2 q E ohm --ts) shin (E?) MAns -Fsh m(41-42)chM(40-41)1e-'n(t-E')} 9 (4-40)? { (?i)?, (ti + 2 2 C?SmAn: nt=1 X [ eh m (Er?t,2) sh m (?Et) sh m ch nt(? ti)] e-in (4-t) } (?4? t),; (34) So It? 2 v-t cosmi o (El 71) ---P2 +5; ?t?2:is MAM tT e-q. gosh m (4-42)] 9 (41-74) a-7W, cji rn,?(Ei,E2), sh m ? t2).. - ? .Only the part of solution (34) for E < E0, which can be identically rewritten in the form (Di ( ?1) ---- { ?to +2 C2p 4/2 A_NI cos mmah2Inal?ts) ma?1-6-6-4) 1.10 (E. T M chm?E2) ?D, chin (ti--E2)] j ($5) 0.6) (3'0 (38) Is of interest for determination of the effective boundary condition at 111.. The first two terms in (38) describe the distribution of the neutron flux in the event of the complete ab- sence of a gap between the active zone and the regulator surface (D2E D1), and the second two terms (in square brackets) describe the variation of the flux upon the replacement of part of the material of the active zone by the material of the gap. Having derived from (38) an expression of flow component normal to the channel surface, we find the value of the logarithmic derivaties lly(ri) on its surface = ti: 480. y(11) )(75 80 11/1 Da 1 eh Et ?0?5111 Rim a, To -O t-ti 'AR, 1 cR, cos mile t M ?11) 1 r t cosmic -""t?-?) th (EI ? t8) X [t +2 Si 2 1-F(D1/Ra)th m(i?gs) j L kSi -rLi m [1 + (DI/Ds) th m -- tx=1 in=1 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 (39) Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 where, according to [10], D (.21 c2 2 ..?331) 2 (ch ,1?cos ros When A = 0, Eq. (39) turns into Eq. (17) for 1/y0 (since as A ? 0, Jr5 R, exp (-4) ? 0, - t2) -.1nRi/R2). Substituting 1/yr and 1/y2 into (15) and performing the integration in the bipolar coordinate system over the variable n, we find the value of the coefficient I(A): 1-8 +n I (A) = .c [ 1 1 1 4 , cd,Ri y? +8 V (n) yoy2 (q) j v-p?-?=v)d- [1+21n =-Li, PA 2Y0 v? -8 -a (40) Let us consider the case of a small gap thickness, 6 Z a c . ,, p GMZ 27 H 1,38 0,16 0,06 100-180 27 D 3,76 0,38 0,14 GMZ 36 H 0,04 0,04 0,01 350-500 6 D 0,13 0,08 0,03 84 H ?0,01 0,05 0,01 350-500 6 GMZ. 2800. so H ?0,02 0.04 0,01 350-500 6 compacted D ?0,10 0,03 0,01 350-500 6 31 H ?0,22 0,05 0,02 350-500 12 D ?0,22 0,03 0,01 350-500 *For a fiducial probability of 0.95. The present paper considers the variation of an important property of graphite, viz., its radiation dimen- sional stability. This is necessary to do since it is usually assessed from the results of tests (especially tests of long duration) of an extremely limited number of samples. It is known that the radiation dimensional stabili- ty, according to [5], is determined primarily by the value of the coefficient of thermal expansion and the degree of perfection of the crystal lattice. However, it is not possible to calculate variation of the dimensional stability by starting from the variational coefficients of the given properties of the graphite; this is because both the properties themselves and their variational coefficients change during irradiation. The situation is also com- plicated by variations in the irradiation conditions, i.e., the temperature, density of the damaging flux, etc. The variation of the radiation dimensional stability, therefore, is evaluated in this paper by statistical treat- ment of the results obtained during irradiation of samples. Graphite of the GMZ grade and its variants were studied. For this purpose, five or more samples 40 mm in length and 4-6 mm in diameter, cut from a single block or from different.blocks, Were irradiated sfinultaneonaly in a common ampul device at Constant temperature and density of damaging flux., The change in the lengths of the irradiated samples was determined. In some cases the samples were irradiated repeatedly in order to obtain the dimensional variations as a function of the dose. The irradiation temperature ranges from 70 to 950?C and the fluence reached a value of 1022 neutrons/cm2.* Along with the small samples in some cases we also studied bulk samples with a length of 100 mm or, more and a diameter of 50-55 mm which were' stood upright in the irradiating arrangement. Reactor channels with identical irradiation conditions were used. Varying the height of the bulk samples, we measured their diameter. Since the samples were chosen not only from the cross section of one block but also from the cross sec- tion of blocks of one production batch and different batches, the samples taken for study are quite representa- tive of the given grade of material. The results obtained from experimental measurements of the relative radiation variation of the lengths of the samples, A///, of various graphites were processed using Student's coefficient. Table 1 gives the arith- metic mean M, rms Sn, and confidence interval Ax. The results of these calculations for bulk specimens with / = 100 mm and d = 50-55 mm are presented in Table 2. For the graphite materials enumerated, the average value of the relative variation of dimensions under irradiation, obtained from tests of no fewer than six samples, characterizes the given material and can be used in calculations. *Here and heneeforth 'the fluence is given for neutrons with E a.0.18 MeV. 535 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 LITERATURE CITED 1. T. K. Pekal'n, Yu. S. Vigril'ev, and Yu. I. Mikhin, in: Graphite-Based Structural Materials [in Russian], No.3, Metallurgiya, Moscow (1967 2. V. N. Barabanov, Yu. P. Anufriev, and N. N. Dergunov, in: Graphite-Based Structural Materials [in Russian], No. 6, Metallurgiya, Moscow (1971), p.35. 3. V. Ya. Kotosonova and G. A. Lushnikov, in: Graphite-Based Structural Materials [in Russian], No. 5, Metallurgiya, Moscow (1970), p.198. 4. Yu. S. Virgil'ev, in: Graphite-Based Structural Materials [in Russian], No. 12, Metallurgiya, Moscow (1977), p. 40. 5. Yu. S. Virgil'ev and I. P. Kalyagina, At. Energ., 31, 497 (1971). TEMPERATURE DISTRIBUTION IN THE RADIATION HEAD OF A GAMMA-TELETHERAPY UNIT A. G. Sul'kin, G. P. Elisyutin, UDC 621.039.538.7.001.5:539.122.173 and M. Sh. Vainberg Gamma teletherapy units are basic technical equipment in modern radiation therapy. The LUCh-1,AGAT- 5, and AGAT-R teletherapy units widely used in the USSR have designs which are standardized to a consider- able extent. Thus, all of these units contain a radiation source with the radioisotope 60Co with a nominal activ- ity of 4000 Ci; the source is housed in a radiation head with a standardized biological shield. For uniform attenuation of the radiation in all directions the biological shield is almost spherical in shape and consists of three layers: a tungsten holder for the radiation source, the main shielding jacket of slugs of depleted uranium, and an external jacket of cast steel. The uranium slugs are hermetically sealed in a sheath to protect them from oxidation which could result in the contamination of the construction elements. It is undesirable to cover the uranium slugs with relatively thick stainless steel sheet since this entails a weakening of the shield at the - Joints. Preference is therefore given to thin metal sheaths applied by electroplating; the strength of such sheaths depends significantly on the degree to which the uranium slugs are heated by the radioactive decay of 60Co. The thermal power dissipated in the mass of the radiation head is determined by the radiant energy and the activity of the radioisotope, self-attenuation of the radiation in the source, and absorption of the radiation in the materials of the shield. The thermal deformations and temperature gradients which arise in the process should not result in emergency situations caused, in particular, by the rupture of the air-tight sheaths of the uranium slugs. In the course of operation the radiation head can be in the irradiation position when the exit window and the end of the source is cooled directly by air. The storage position when the exit window is closed is less favorable. Even with operation in two six-hour shifts, with allowance for the additional time for positioning the patient and adjusting the unit, the radiation head is in the storage position for no less than 8100 of the entire operating time. Owing to the short duration of the irradiation (2-10 min) and the high inertia of the thermal processes, it may be assumed that the relevant thermal characteristics under storage and irradiation condi- tions differ very little from each other in practice. For these considerations the experiment was conducted under conditions which simulated primarily the storage conditions of the source. The temperature of the radiation head was measured in one technically ac- cessible radial direction since under storage conditions the temperature distribution in the head may be taken to be practically isotropic and the problem of determining the temperature distribution may be considered to be one-dimensional. The thermal state of the standardized biological shield in the radiation heads of the domestic gamma teletherapy units LUCh-1,AGAT-S, and AGAT-R was studied on the identical radiation head of the RAD-1 unit which has the same biological shield and is designed to hold a 60Co source with a nominal activity of 4000 Ci. Translated from Atomnaya Energiya, Vol. 44, No. 5, pp. 463-464, May, 1978. Original article submitted July 4, 1977. 536 0038-531X/78/4405-0536 $07.50 ,0 1978 Plenum Publishing Corporation Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Fig. 1 0 2 4 6 8 10 Distance from end of source, cm Fig. 2 12 Fig. 1. Experimental arrangement: 1) rotational gamma teletherapy unit; 2) cone with built-in thermocouples; 3) radiation sources; 4) radiation head. Fig. 2. Temperature distribution over radius of shielding jacket of gamma teletherapy unit. During measurements of the temperature the source activity was 2010 Ci and its thermal power was 30.9W since the specific energy release of "Co is 0.0154 W/Ci [1]. The experimental arrangement is shown in Fig. 1. The radiation head was rotated on the stand of the unit with the exit window pointed upwards, the diaphragm was removed from it (without disturbing the elec- trical connections), the shutter was opened from the control panel so as to release the radiation beam, and then a cable and a system of control pulleys were used to insert the cone into the exit window; this cone, whose size corresponded to that of the window, had four (Chromel?Copel) thermocouples (Fig. 2) at various levels. One of the thermocouples was built into the end of a rod running through the center of the cone; the purpose of this thermocouple was to measure the temperature of the source ampul. The cone fitted tightly into the window of the radiation head, thus ensuring reliable thermal contact be- tween the cone and head. Stable temperature conditions were established in the course of one hour. The air temperature in the premises was 22?C during the measurements. An EPR-09MZ potentiometer was the recording instrument. The error of measurement with allowance for the compensating coil error and the recording error did not exceed 3?C. Solid cones of tungsten and of steel as well as a hollow conic vessel were tested. The results of measure- ments for the tungsten and steel cones practically coincided whereas lower temperatures were obtained for the hollow cone which simulated the conditions of long irradiation (practicable only for phantom measurements). The results of temperature measurements in the radiation head (by using solid cones) are given in Fig. 2. The temperature of the radiation head where it comes in contact with the radiation source was 36?C, which was 14?C above room temperature. Proceeding from this, we can estimate the maximum temperature of the slugs in the shield for a source with a 4000-Ci 60Co source. Although the relation between the maximum temperature of the slugs in the shield and source activity is nonlinear owing to the dependence of the heat-transfer coeffi- cient on the temperature of the radiation head surface and the air in the premises, in the temperature range under consideration the nonlinearity has an insignificant effect [2]. Therefore, when the source activity is raised from 2010 to 4000 Ci the difference between the temperature of the shield and that of the surroundings may be assumed to increase in the same proportion, and then the maximum temperature of the shield at the place of contact with the ampul surface is 50?C. The error resulting from the assumption that the heat-trans- fer coefficient is constant in the temperature range considered does not exceed +15% and thus in fact the maxi- mum shield temperature may prove to lie within the limits 48-50V. Bearing in mind that 1) according to current standards the activity of the radiation source at the time of installation may differ from the nominal value by up to +20% (which corresponds to roughly 6?C), that 2) accord- ing to the technical conditions the capability of gamma teletherapy units to operate should not be affected at an 537 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 ambient temperature of up to +40?C, and that 3) the error of measurement at an activity of 2010 Ci was *3?C, we may take tmax = 50 +,/62 + 182 + 62 LI. 70?C to be the maximum temperature for the shield in the radiation head of domestic gamma teletherapy units. LITERATURE CITED 1. G. M. Fradkin, V. M. Kodyukov, and A. 0. Ragozinskii, in: Radiation Technique [in Russian], No. 1, Atomizdat, Moscow (1967), p.5. 2. M. A. Mikheev and I. M. Mikheeva, Fundamentals of Heat Transfer [in Russian], Energiya, Moscow (1977). 538 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 INTERNATIONAL COOPERATION SOVIET ? JAPANESE COOPERATION ON THE PEACEFUL USES OF ATOMIC ENERGY 13. A. Semenov The Soviet Union cooperates with many countries on the peaceful uses of atomic energy. Under the terms of some 35 agreements signed with other countries the Soviet Union is engaged in extensive scientific contacts, exchanges of delegations, joint scientific research, the design and construction of various installations, nuclear reactors, etc. The use of atomic energy for peaceful purposes is an area of science, technology, and econom- ics in which the Soviet Union and Japan have had great achievements. Japan has built up a considerable atomic power industry (the total installed capacity of the atomic power plants is about 8000 MW) and atomic engineering industry. A fast experimental reactor (JOYO) and a heavy- water reactor (Fugen) have been developed and constructed. Work is under way on nuclear fuel processing and research is being conducted on controlled thermonuclear fusion. All of this provides prerequisites for the de- velopment of cooperation between the USSR and Japan on the peaceful uses of atomic energy. Until recently, such cooperation did not have legal formulation but specialists had already been in con- tact. Thus, as the result of an agreement, a delegation of representatives of Japanese atomic science and technology, led by T. Doko, Vice-President of the Atomic Industrial Forum of Japan, visited the Soviet Union in June, 1973. The purpose of the visit was to allow the delegation to become acquainted with the scientific and industrial centers in the nuclear power field, the state of the art, and the prospects for future develop- ment. During the visit the delegation saw scientific research institutes engaged in research on nuclear reac- tors, atomic power plants, and power engineering works. The delegation had talks with A. M. Petros'yants, Chairman of the State Atomic Energy Committee of the Council of Ministers of the USSR (GKAE SSSR), and Soviet specialists. During a return visit in January, 1974, a Soviet delegation led by L D. Morokhov, First Deputy Chair- man-of the GKAE SSSR, familiarized itself with Japanese scientific centers and enterprises and had talks with eminent industrial and government figures. At the request of the Atomic Forum a delegation visited the Soviet Union in January, 1975, to acquaint itself with problems of atomic power plant safety and radiation safety. The delegation visited the leading Soviet institutes working in this field, atomic power plants, and a station for radioactive waste burial, and also had talks in the GKAE and the Ministry of Power and Electrification of the USSR. Before its departure the delega- tion was received by the Environmental Protection Commission of the Supreme Soviet of the USSR. These contacts and exchanges enabled the specialists of our countries to become more familiar with the successes achieved in both our countries and to discuss the possibility of concluding an agreement on coopera- tion between the GKAE and the Atomic Industrial Forum. During a visit to Moscow in June, 1977, T. Doko, President of the Federation of Economic Organizations of Japan, and his talks with A. M. Petros'yants as well as in subsequent discussions with the Atomic Forum both sides drew up a draft agreement; and in November, 1977, a Soviet delegation headed by A. M. Petros'yants visited Japan to conclude the agreement on cooperation on the use of atomic energy for peaceful purposes. Dur- ing the visit the delegation had discussions with officials of the Atomic Forum, had talks with the Ministers of Scientific Research and Technology, Foreign Affairs, and External Trade and Industry. The Soviet delegation also visited atomic research centers (Tokyo Research Center of the Japanese Atomic EnergyResearchInstitute JAERI, the Oarai Engineering Center of the State Corporation for the Development of Power Reactors and Nuclear Fuel PNC); firms working in nuclear power, research centers, and factories producing atomic power plant equipment (Mitsubishi in Kobe, Sumitomo and Ikawajima Heavy Industries in Yokohama, and Hitachi in Hitachi); atomic power plant (Tsugura, Mikama, and Fugen) with boiling, water-moderated?water-cooled, and heavy-water reactors, as well as the JOY() fast reactor. Translated from Atomnaya nergiya, Vol. 44, No. 5, pp. 465-466, May, 1978. 0038-531X/78/4405-0539 $07.50 01978 Plenum Publishing Corporation 539 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Two meetings were held with prominent figures of the Federation of Economic Organizations and the Atomic Forum. During these meetings both sides informed each other about the development of the nuclear power industry in their countries, discussed the possibilities of economic cooperation, and also went into the subject matter which could be of greatest interest for mutual cooperation. The GKAE and the Atomic Forum agreed that a program of cooperation for a period of two to three years under the signed agreement would be drawn up in the near future and both countries would proceed to implement it. In the course of the visit to Japan the leader of the Soviet delegation gave a lecture for the Japanese Scientific Society on the development of nuclear power in the USSR; a press conference was held and there was a working meeting with members of the Japanese parliamentary committee on science and technology. The visit of the Soviet delegation was concluded with the signing of an agreement on cooperation in the domain of the peaceful use of atomic energy. On behalf of the Soviet side the agreement was signed by A. M. Petros'yants and on behalf of the Japanese side by H. Arisawa, President of the Atomic Forum. The signing ceremony was attended by the Soviet Ambassador to Japan, D. S. Polyanskii, and T. Doko. The agreement will make it possible to organize sceintific and technical cooperation in such major areas of atomic science and technology as power reactors and controlled thermonuclear fusion. At its first session in Tokyo in January, 1978, the Soviet?Japanese Commission on Scientific and Tech- nical Cooperation discussed various aspects of the cooperation between Soviet organizations and official Japan- ese organizations within the framework of the 1973 Agreement on Scientific and Technical Cooperation. The discussion dealt with a number of regions of mutual interest, including the peaceful use of atomic energy. The Commission set up a working group on atomic energy to discuss and prepare proposals on concrete subjects and forms of cooperation. Soviet?Japanese cooperation in the realm of atomic science and technology will thus be implemented in accordance with the agreement with the Atomic Forum whose membership consists of some 700 firms and economic and research organizations of Japan as well as on a governmental level within the framework of the intergovernmental agreement on scientific and tecnnical cooperation. 540 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 CONFERENCES, MEETINGS, AND SEMINARS INTERNATIONAL SEMINAR ON THE TECHNOLOGY OF sopIum COOLANT V. I. Kondrat'ev and Yu. V. Privalov A seminar with the participation of some 30 scientists and specialists from the USSR, Belgium, and the Netherlands was held in Dimitrovgrad in October 1977. The successful development of fast reactors at the present time is determined in great measure by achievements in solving problems of sodium technology. The high cost and great complexity require the collaboration of scientists of various countries. This seminar marked one stage in such collaboration. The seminar heard 18 papers on problems of sodium purification from impurities, indication of leaks from sodium?water steam generators, corrosion and mass transfer of steel into sodium, safety of sodium loops, and the behavior and analysis of impurities in sodium. In a review paper V. M. Arkhipov (USSR) gener- alized the experience from sodium technology of the BR-5, BOR-60, and BN-350 reactors, concerning the preparation of the coolant, its contamination during start-up and initial operation as well as normal operation, elimination of the consequences of breakdowns and washing off the equipment, sampling, and extinguishing sodi- um fires. Sodium fire extinction was discussed in greater detail in a paper by I. G. Kobzar (USSR). M. Van Hasselt (Netherlands) told of experience of work with sodium on experimental stands, formulated requirements on the purity of sodium coolant which would be safe from the point of view of corrosion, and drew the conclusion that "cold" traps can ensure the required purity in respect of impurities (in this case, carbon as well) in addition to purification from products of the water?sodium reaction. F. Castilles (Belgium) presented the results of tests of structural materials in nonisothermal dynamic sodium systems using foils to determine the activity of carbon, noting that the activity of carbon in a nonisothermal loop is determined by the tempera- ture of the "cold" trap. The plastic properties of stressed ferrite steel are improved by long holding (22,000 h) in a stream of moving sodium at 700?C. A paper by V. Kolster (Netherlands) was devoted to experimental sub- stantiation of the required sodium purity in respect of oxygen. Papers by M. Van HasseIt (Netherlands), M. Coenen and F. Livens (Belgium) devoted much attention to instrumental and chemical methods of impurity monitoring, methods which are at a high technical level in those countries. The extensive experience of Soviet researchers in the purification of sodium coolant by "cold" and "hot" traps, of inert gas, and of coolant and gas from radioactive impurities, and optimization of purification systems was presented in papers by F. A. Kozlov and V. F. Bargetsov. F. Meyer and J. de Bries (Netherlands) reported on interesting developments of acoustical methods of monitoring water leaks in steam generators and monitoring sodium boiling in reactor core packets. In their opinion, which coincides with the point of view of Soviet specialists, these methods can be used to establish water leaks with a flow rate of more than 0.2 g/sec. The system for leak indication in industrial steam genera- tors should, therefore, be a complex system using both concentration-measuring and acoustical methods. The advisability of using a leak indication method based on measurement of the increased hydrogen concentration in the gas cavity of the loop was shown in a paper by Yu. V. Privalov (USSR). The kinetics of reactions of carbon-containing gases with sodium and the chemical equilibrium in the sodium?oxygen?hydrogen system were described in papers by Yu. I. Zagoruliko and Yu. V. Privalov (USSR). Noteworthy attention was paid to the safety requirements during development of equipment for the SNR-300 for recharging and storing spent fuel elements in sodium (paper by M. Deboche, Belgium). The final session summed up the work of the seminar and pointed out its usefulness. The participants exchanged views about the state of the art and further development of work in their countries on fast reactors and expressed a desire to hold joint seminars in the future. Translated from Atomnaya Energiya, Vol. 44, No. 5, pp. 466, May, 1978. 0038-531X/78/4405-0541$07.50 ?1978 Plenum Publishing Corporation 541 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 IAEA ACTIVITIES ON HIGH-TEMPERATURE REACTORS V. N. Grebennik A Technical Committee on High-Temperature Reactors met in Vienna in December 1977. The meeting, which was convenedby the IAEA and was held within the framework of the nuclear power and reactor section, was attended by 23 specialists from Austria, Belgium, France, the Federal Republic of Germany, Japan, the Netherlands, Poland, Switzerland, the USSR, the United Kingdom, the USA, and two European organizations, the CEC and the OECD/NEA. Heeding the interest in the development of the concept and prospects of the in- dustrial application of these reactors, the IAEA invited the countries most active in this area to participate in the work of the Technical Committee to draw up recommendations for future work on NTR and to set up an international working group. In the course of the work of the Agency over recent years a number of working groups on various subjects were set up. The function of these groups includes exchanging information about national program and concrete technical problems, working together with the Agency to organize conferences, symposia, and meetings of specialists on the most pressing problems, and to provide other assistance. The activities of the Working Group on HTR will be extended to helium-cooled thermal reactors for the production of electricity and technological heat as well as to CO2-cooled reactors and fast helium reactors to the extent that they are not encompassed by other international organizations and working groups. It will be the task of the International Working Group to discuss the overall strategy program for HTR development, planning re- search, (considering problems of the design, construction, and safety and operational aspects of atomic power plants, the technology of the fuel cycle, and considering the areas and processes of application of thermal energy from HTR. At its meeting, the Technical Committee considered national HTR programs and discussed papers on special topics of particular interest at this time (constructional and operational experience, promising fuel cycles, achievements in the application of thermal energy from HTR, etc.). The papers and communications presented by experts provided information about HTR already in existence, under construction, or on the draw- ing boards. As before, the AVR (Federal Republic of Germany) with a power of 15 MW(E), which employs spherical fuel elements, is operating stably. Over the past 3.5 years AVR has been operating with helium at a tempera- ture of 950?C with a power factor of 0.8-0.9. The construction of the prototype THTR-300, which will have a core of similar design, is to be completed in 1980. The delay in the completion of the reactor in comparison with previously set deadlines (1978-1979) has been due to the fact that additional safety requirements have been introduced into the project. Intensive testing is continuing on the reactor of the Fort Saint Wrane Atomic Power Plant (U.S.A.) which has a power of 330 MW(E) and operates on slug-type fuel elements. Over a period of 1 year (from mid-1976 to July 1977) the reactor periodically (-30% of the time) operated at 28-30% power. Once the difficulties of the start-up period were overcome and corrections were made for the malfunctions caused by the conventional steam power-generating equipment and specific malfunctions of the plant (internal leak- ages of helium in gas blowers, overheating of the reactor vessel at the places where the control and safety system passes through, the distribution of gas flows in the thermal insulation), the reactor reached 40% power in August 1977. It operated at this level for about two months. At the end of October, 1977, permission was obtained to increase the power to 70% and this level was attained. It is assumed that the reactor will reach nominal power in 1978. In Japan work is under way on an experimental very-high-temperature reactor VHTR with a power of 50 MW(T) at a helium temperature of 1000?C at the outlet. Construction is to begin in 1978. As part of the proj- ect studies are to be made on processes of direct reduction of iron by using the heat from the VHTR. In the Soviet Union, work is being done on an experimental high-temperature energy-technological facility with a reactor power of 50 MW (electrical) and on a high-power prototype reactor operating on thermal and fast neu- trons. Translated from Atomnaya nergiya, Vol. 44, No.5, pp. 467-468, May, 1978. 542 0038-531X/78/4405-0542$07.50 ?1978 Plenum Publishing Corporation Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 The effects of the advanced countries in promoting the HTR concept in recent years have been charac- terized by the concentration of extension of work in the area of the most effective commercial application of this type of reactor. Some countries (the U.S.A., the Federal Republic of Germany, Switzerland, etc.) are working on the use of the HTR for the generation of electricity, preference being given in this case to the more promising gas-turbine cycle which ensures higher efficiency and makes effective use of air cool- ing. In the Federal Republic of Germany, Japan, the USSR, France, and the U.S.A. most intensive work is being done on the energy-technological application of such reactors in chemistry, metallurgy, and other branches of industry, for long-diRtrnac?,! transmission of thermal energy, etc. The introduction of HTR in these areas is based on the procluenn of hydrogen and synthetic fuel by gasification of coal and decomposi- tion of water. At the present time intensive studies are being made primarily on topics which bear on the commerical introduction of the reactor: development of a fuel cycle, design of equipment and plant (vessels of prestressed concrete, gas flowers, heat exchangers, conduits of the control and safety systems, etc.), sub- stantiation of the safety and reliability of atomic power plants, licensing, etc. In some countries work began in 1977 on changes in HTR fuel cycles in connection with the requirement of nonproliferation of atomic weapons. The fuel cycle envisaged for reactors in operation, under construc- tion, or in the design stage is one which ensures a high coefficient of conversion with the use of highly enriched uranium (-93$ and thorium. As the result of new limitations on the enrichment of fuel for nuclear power it is proposed that the HTR operate with a uranium?thorium cycle in which the uranium enrichment is about 20% as well as with a cycle based on low-enriched uranium (5-10%4. Work has begun on the technology for fabricating microparticles out of fuel with the new composition. A license for the industrial use of this fuel, especially in the reactor of the Fort Saint Wrane Atomic Power Plant, is to be obtained after 1980. The commerical intro- duction of large HTR in some of the most advanced countries in this area (Federal Republic of Germany, the U.S.A., etc.) is expected to begin in the late 1980s ? early 1990s. It is proposed to use these reactors, which have higher efficiency and more economic fuel cycle, for electric power generation (Nei = 1200-1300 MW) and especially for the production of industrial heat (NT ? 3000 MW). Large prototype plants for the energy-tech- nological use of HTR operating with a gas-turbine cycle are to be built within the next decade. In the opinion of specialists, the process employing high-temperature heat from an HTR which is best mastered at the pres- ent time and which is proposed for immediate introduction evidently will be the process of obtaining synthetic gaseous or liquid fuel from coal. This is considered as one of the principal directions in the program to en- sure future energy supplies in countries with considerable reserves of lignite and coal. The meeting of the Technical Committee discussed a possible strategy for the development of nuclear power involving HTR and fast helium breeder-reactors with a short fuel doubling time. Work being done on fast reactors within European groups is devoted primarily to the study of safety, completion of the main de- sign features, and reactor tests on the effect of high fluxes on the structural materials and fuel compositions. The International Working Group on HTR drafted a program of work and recommended that meetings of specialists be held within the fremework of the IAEA in 1978-1979 to consider the most urgent aspects of IITR: this will enable specialists of various countries to exchange views and to discuss concrete problems andways of solving them. It was decided to invite specialists of Italy, Spain, and Sweden to participate in the Working Group on HTR in 1978. The breadth of possible applications of HTR and the large volume of research entailed are inducing many countries to unite their efforts in order to concentrate the work and to reduce the time and expense of research and construction of facilities. International collaboration within the framework of the IAEA is an important condition for the successful development of the conception of HTR. The activities of the International Working Group on IITR set up by the IAEA will be aimed at providing all-round assistance in this field. 543 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 MEETING OF IAEA EXPERTS ON THERMONUCLEAR REACTORS G. N. Popkov The meeting, which was held in Madison, Wis. , in October 1977, considered plans for thermonuclear reactors under development at the present time. These included plans for: 1) the TFTR, JT-60, JET, and T-10M facilities which will be built after T-10 and PLT. These facilities should yield reactor plasma param- eters; 2) reactors for achieving ignition of a thermonuclear reaction and for studying the interaction of a par- ticles with plasma. It is planned to build them after facilities of the TFTR and JET type; 3) reactors for study- ing tritium breeding, processes which occur in the blanket and point to the possibility of producing electrical energy for external consumers; 4) demonstration reactors, i.e., prototypes of thermonuclear power plants, demonstrating the economic feasibility of constructing competitive thermonuclear power plants. The partici- pants in the meeting focussed their attention on the projects mentioned in points 2 and 3. Information papers about the state of development were presented on four projects from point 1; demonstration reactors (point 4) have been sufficiently developed. At the plenary sessions 24 papers were devoted to plans for, and individual engineering and technologi- cal aspects of, reactors of the tokamak type, nine papers dealt with reactors with inertial confinement, four papers to reactors based on open traps, and six, to economic aspects and planning. The rest of the papers concerned engineering-physical problems and reactors of other types. Following the U.S.A. and the Soviet Union, Japan and West European countries have started drawing up programs for the construction of thermonuclear power stations based on a tokamak. The Japanese program considers two possibilities of attaining the goal: quickly taking the first step on the basis of present-day tech- nology without the use of superconductors or the simultaneous solution of physical and engineering problems (with the use of superconductors), but at a slower pace. The European program envisages parallel construc- tion of-facilities satisfying the requirements of points 2-and 3, using the same engineering designs in them wherever possible. Work on both programs is far from being completed Tokamaks are the most promising and have been developed with the greatest depth. The plasma param- eters obtained in them have drawn considerably closer to thermonuclear parameters and optimization of the projects is proceeding along the lines of bringing the characteristics of future reactors close to those attained on existing facilities. Thus, the ratio of the process duration required for the reactor to that obtained experi- mentally in 1974 was reduced from 10,000 to 60. The ion temperature and the energy confinement parameter wr is only one order of magnitude smaller than that required for the reactor. Plans for tokamak thermonuclear reactors are being improved: Their dimensions are being reduced and their construction simplified. This can be traced most clearly in the work of the University of Wisconsin, Argonne National Laboratory, and Princeton Laboratory. The plans they presented contain no diverter and the control windings have been moved outside. The power cycle has been reduced to ?60 sec and the geometric dimensions have been reduced by increasing the toroidal magnetic field. It was noted that simplification of the design could make the tokamak competitive. As the design studies are gone into more deeply, economic calculations begin to take up more space. Several papers were presented in computational codes which make it possible to solve the problem of obtaining the required plasma parameters at minimum cost. It should be noted that although all the codes yield accurate results, with such a method of ea lculation it has been possible to optimize the parameters and quite accurately predict the costs of TFTR. The meeting had five sections: tokamak thermonuclear reactors, demonstration and commerical tokamak power reactors, thermonuclear reactors with magnetic confinement, reactors with inertial confinement, and the role and place of thermonuclear reactors. Experimental data on many parameters permit them to be extrapolated quite reliably to reactor values. In this case acceptable results are obtained even for pessimistic versions of the prediction. Accurate design Translated from Atomnaya nergiya, Vol. 44, No. 5, pp. 468-469, May, 1978. 544 0038-531X/78/4405-0544$ 07.50 ?1978 Plenum Publishing Corporation Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 of power reactors requires further development of plasma physics; explanation of the dependence of the energy lifetime on the ion temperature; a study of the plasma-wall interaction and methods of protecting the plasma from impurities; a full-scale experiment on auxiliary plasma heating; study of how nuclear reaction products, especially a particles, behave in plasma. The section on the role and place of thermonuclear reactors discussed the problems and prospects of both pure and hybrid thermonuclear reactors. Particular attention was devoted to safety, economic and social problems, the existence of fuel and material resources, and the economic characteristics of research pro- grams. The opinion that pure thermonuclear reactors are safer than other nuclear facilities found received fur- ther confirmation. The ecological aspects have been worked out much better. Considerable success has been achieved in understanding the place and prospects of the hybrid thermo- nuclear reactor. The safety of such reactors differs little from the analogous problems of fission reactors. Hybrid reactors can be built upon the basis of tokamaks, systems with inertial confinement, and apparently on the basis of mirror traps. An appropriate program is thus far being drawn up only in the USSR. The meeting of experts noted the desirability of: drawing up a program providing for a considerable fraction (e.g., 10070) of the world power requirements to be covered by thermonuclear reactors by the beginning of the 21st century; constructing facilities for technological tests; developing materials with an operating life of more than 10 MW ? yr/m2; increasing the energy-intensity of reactor elements; and developing methods of replacing the first wall and the blanket. Note was taken of the need to accelerate the development of facilities of later generations so that ready facilities could be entered into the world energy balance by the beginning of the 21st century when the potential demand may exceed the power of the energy sources. SEVENTH INTERNATIONAL CONFERENCE ON ATOMIC COLLISIONS IN SOLIDS V. M. Ohicherov The conference was held at Moscow State University in September 1977. About 80 out of the 240 papers presented at the conference dealt with the interaction of plasma with the first wall of a thermonuclear reactor. In review papers M. Kaminsky (U.S.A.) and R. Berisch and A. Scherzer (Federal Republic of Germany) dis- cussed the results of research done in various laboratories. At the present time further progress in the most advanced area of thermonuclear research, tokamaks, depends on whether it will be possible to decrease the interaction of the plasma with the wall of the device. The problem includes protection of the plasma from the effect of the wall (reduction of the number of impurity atoms which cool the plasma) and protection of the wall from the destructive effectof the plasma (extension of the wall lifetime). In devices of the present generation the most important thing is to reduce the flow of impurity atoms from the wall into the plasma. This flow is the result of elementary processes which in themselves have been studied for quite some time now. The problem now is to combine the research on elementary processes done in monokinetic beams of particles with research done in plasma devices. To do this it is necessary to have detailed data about the fluxes of particles bombarding the chamber walls in tokamaks. In their review paper R. Berisch and A. Scherzer considered the conditions at the boundary of plasma in a toroidal device and gave the result of measurements of the fluxes of energy, hydrogen atoms, and impurity atoms in the shadow of the diaphragm in the DITE and TFR devices. It is noted that the measurements are diffi- cult to interpret and the estimates obtained from them for the fluxes (1015-1016 atoms/cm2- sec for hydrogen and 1011-1013 atoms/cm2- sec for impurities) are quite rough. The fluxes of particles and their energy distribu- tions depend on the conditions for the discharge. Translated from Atomnaya Energiya, Vol. 44, No. 5, pp. 469-470, May, 1978. 0038-531X/78/4405-0545$07.50 ?1978 Plenum Publishing Corporation 545 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Approximately such fluxes of hydrogen ions on the wall are expected in future reactors. The energy of the particles will probably lie in the range from 1 eV to 100 keV. All possible angles of incidence of particles on the surface will be realized. Some fraction of the particles will be reflected continuously from the surface and will return into the plasma whereas the remainder will be captured by the material of the wall. When plasma interacts with the wall the following occur: 1) desorption of atoms of the surface layers by ions, electrons, and electromagnetic radiation; 2) sputtering (physical and chemical); 3) back scattering of ions; 4) capture of ions by surfaces and reemission of gas atoms; 5) surface changes due to prolonged ion bom- bardment (e.g., blistering); 6) evaporation and breakdown of material as the result of surface overheating. Desorption data for the greatest part concern electron and photon desorption from well-prepared, smooth surfaces, and very few studies deal with ion desorption. Back scattering of ions is studied by calculations and good agreement with experiment in the energy range 1-10 keV gives rise to confidence in the calculations in the region of 100 keV where measurements are very difficult to make. In the case of scattering of hydrogen ions by various metals the experimental values of the particle reflection coefficient and the energy reflection coefficient are about 10% with an incident particle energy of about 1 keV. Insufficient reliable data are available on sputtering by hydrogen ions and there are no data at all on sputtering by tritium. The data that are available concern pure metals above all. It seems more promising, however, to search fora material with a low sputtering coefficient among compound substances: borides, car- bides, and nitrides of light elements of their alloys. Moreover, the search is hindered by the fact that the angular and energy distribution of the bombarding particles from the plasma are now known. Meanwhile, the maxima of the calculated curves for the sputtering coefficient for some compound materials lie at different energies of bombarding ions. Recent measurements on sputtering by neutrons yielded a coefficient of less than 10-4 atoms/neutron. "Small pits" will not be formed under irradiation of a polished annealed surface. In such a surface the stresses in the surface layer were removed and the microcracks eliminated. Chemical sputtering is a quite strong process and poses great danger to low-Z materials: graphite, car- bides, and insulators which have a high reactivity with hydrogen and oxygen ions. Such sputtering is tempera- ture-sensitive as is any mechanism including chemical reactions. For example, sputtering of pyrolytic graphite by hydrogen ions is maximum at 400-800?C (S ? 0.08 atom/ion for 2-keV H+ ions). It may be possible to reduce surface erosion due to chemical sputtering by choosing and maintaining an optimal surface tempera- ture. It is difficult to say at this time, however, to what extent it will be possible to utilize this effect. Intensive studies are being conducted on methods of reducing surface erosion by blistering. For a long time, blistering was considered to be a serious mechanism of erosion in future reactors since it was assumed that this process can be repeated many times. These ideas were based on experiments in which irradiation was carried out with monoenergetic ions. It was recently established, however, that blistering is effectively suppressed when metals are irradiated with particles with a broad energy spectrum which apparently will be the case in the reactors. The suppression is due to the uniform distribution of vacancies over the thickness of the irradiated material and the formation of a porous structure allowing gas to escape from the depth, thus preventing further blistering. The emergenceof a porous structure and the absence of blistering were also observed during irradiation of metals at a quite high temperature (up to 0.4-0.5 of the fusion point). It is not clear, however, whether such a high wall temperature will be maintained in reactors. Blistering is reduced appreciably in materials with small grains (and dispersed second phase), such as sintered beryllium and alu- minum powders. Hydrogen and impurity atoms and ions bombarding the first wall during discharge in turn causes desorp- tion and sputtering of adsorbed layers and the metal of the wall, reproducing and increasing the quantity of im- purities in the plasma. At the present stage the impurity concentration in the plasma is much higher than in the gas filling the chamber prior to the discharge. To create the conditions necessary for a self-sustaining reaction to be initiated, the impurity concentration should be reduced many times. Contaminating oxygen and carbon atoms apparently enter the plasma as the result of desorption of H20, CO, CO2, and hydrocarbons from the chamber walls. It is, therefore, natural to try to have a chamber with as clear walls as possible prior to the discharge. A promising method of purification from impurities under consideration is that of irradiating the metal surface with streams of atomic hydrogen and forming volatile compounds which can then be pumped off. This method is implemented to one extent or another in plasma de- vices during conditioning discharges in hydrogen with low parameters: Te ? 3 eV, ne ? 1012 cm- 39 T -dis ? 1-10 kA. This method is used successfully to cleanse chambers of oxygen in the DITE and Alcator devices. It was 546 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 discovered, however, that as the oxygen concentration in the plasma decreases, the concentration of metallic impurities increases and this impairs the plasma parameters even more. The increase in the flux of metal atoms in the plasma can be explained in part by sputtering of the chamber wall stripped of its protective coat- ing of foreign atoms. Research thus is being done on effects which may result from embrittlement of the sur- face of metals irradiated with streams of atomic hydrogen. It is now known, e. g., that embrittlement of metals in hydrogen may cause scaling and ejection of considerable numbers of very small metal particles. This example shows that the problem of impurities may become even more difficult when the wall becomes cleaner. As before, processes which occur when various forms of particles and radiation act upon a metal sur- face at the same time, e.g., during simultaneous bombardment of the surface with hydrogen ions and heavier ions, remain unstudied. The proceedings of the conference, which are to be published, will undoubtedly be of interest to special- ists working on controlled thermonuclear fusion. FIRST INTERNATIONAL SEMINAR ON USE OF PROTON BEAMS IN RADIATION THERAPY The seminar was organized by the State Committee of the Council of Ministers of the USSR on Atomic Energy (GK4 and the Academy of Medical Sciences of the USSR (AMN SSSR) and was held in the Oncological Scientific Center of the AMN SSSR (Moscow) in December 1977. Physicists and clinicians have been working for more than 20 years now on the use of proton beams in medicine. By virtue of the characteristic of the interaction with matter, proton beams make it possible to form in the patient's body clearly delineated dose fields with a prescribed shape and a high boundary gradient. This opens up a unique capability for striking targets (tumors) situated in any part of the patient's body without damaging a number of nearby critical organs and structures or the organism as a whole. A great deal of radiobiological experience has been accumulated throughout the world to date from the use of protons and from the radiation treatment of more than 2500 patients. Research and clinical work in the Soviet Union are being done on the basis of the accelerators of the Joint Institute for Nuclear, Research (JINR), the Institute of Theo- retical and Experimental Physics (ITEF), and the B. P. Konstantinov Leningrad Institute of Nuclear Physics, Academy of Sciences of the USSR (LIYaF). The use of proton beams in clinical diagnostics, in addition to radiation therapy, is extremely promising. Short-lived radionuclides (1231, 11C, 150, etc.) produced in proton accelerators can be used effectively for this purpose. In many cases, proton beams reveal fine topographical?anatomical structural differences in organs and soft tissue which are not identified by x-ray examination (proton radiography). For the first time in world practice, extensive information on all of these topics was presented at the seminar. A. I. Ruderman spoke of the experience from proton therapy in the USSR. A review of the scientific and technical aspects of the application of protons in therapy was presented by B. Larrson (Sweden). In addi- tion to Soviet clinicians (E. I. Minakova et al., B. A. Konnov et al., E. E. Marienbakh et al., V. N. Kiseleva et al., G. D. Zarubel et al., B. V. Astrakhan), who reported on approaches to the effect of radiation on vari- ously located tumors, clinical experience with the use of proton beams was described by American researchers (R. Kelberg, H. Suit et al., J. Castro et al.). Some papers were devoted to proton radiography (I. P. Kalshnikov et al., USSR, R. Martin, U.S.A.; J. Saudinoce, France) and the production of radionuclides. The distinctive characteristics of proton beams and the accelerators that generate them require funda- mentally new approaches to physicotechnical provision for their clinical use. The cardinal problems in this area are those of shaping and measuring dose fields and creating special accelerators and special-purpose medical equipment (radiation stands). In addition to the review by M. F. Lomanov, 12 papers were presented by Soviet Translated from Atomnaya Energiya, Vol. 44, No.5, pp. 470-471, May, 1978. 0038-531X/78/4405-054 7$ 07.50 01978 Plenum Publishing Corporation Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 547 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 and foreign scientists on the first topic. An interesting paper on the principles underlying the choice of param- eters and type of a special method accelerator was presented by L. L. Gedin. A separate section of the seminar was devoted to the radiobiological aspects of the application of protons (papers by L. Reyes, Sweden; S. P. Yarmonenko, USSR; M. Raju, U.S.A., etc.). Interesting microdosimetric approaches to the radiobiological problems were presented in a review paper by V. I. Ivanov. The successes achieved in the application of proton beams in medicine confirm the need to extend the use of this form of radiation in clinical practice. It is not surprising, therefore, that part of the papers dealt with the construction of special-purpose complexes on the basis of existing accelerators in the USSR, the U.S.A., and Sweden (V. P. Dzhelepov et al., I. V. Chivolo et al., B. A. Konnov et al., B. Larrson et al., C. Liman et al.) and construction of a complex with a special medical accelerator in the USSR (I. V. Chivilo et al.). The seminar was the first representative forum devoted to this subject, was extremely interesting, and enabled scientists of various countries to share the experience gained in research in the most humane area of modern applied physics. The proceedings of the seminar are to be published by Atomizdat in 1978. IAEA MEETING ON THE USE OF PHYSICAL STANDARDS P. I. Fedotov At a meeting in Vienna, Austria, in August 1977, IAEA experts discussed a report and recommendation on the use of physical standards during inspections and measurements of nuclear materials. They discussed the physical standards employed in nondestructive methods of analysis by IAEA inspectorates and operators of enterprises in order to determine the quantity of materials. The meeting was attended by experts and ob- servers from Great Britain, Belgium, Bulgaria, the Netherlands, the Federal Republic of Germany, France, the USSR, the U.S.A., and Euratom. - - - The report prepared consists of four sections. The first considers the types of nuclear materials in- spected and the nondestructive methods of analysis appropriate for them and discusses the criteria which de- termine the priority in the preparation of standards. Tables have been drawn up with data on the expected error of measurement for various nuclear materials and methods of analysis. The diversity of materials analyzed and methods of analysis require a large number of physical standards to attain the necessary accu- racy of measurement. In view of the high costs and difficulties owing to transportation, preparation and storage, criteria are presented for determining the priority in the preparation of standards: 1) the strategic importance, number and frequency of inspections of the nuclear material; 2) the maximum indeterminacy in striking the nuclear balance, this being due to error; 3) increased accuracy of measurement which can be attained by using a new standard; 4) the reduction which can be attained in the time and cost of inspection by application of the standard; 5) the universality of the standard. On the basis of these criteria, data on the specific properties of the nuclear materials and the character of the production IAEA will establish the priority in the preparation and provision of physical standards. The second section is devoted to the preparation and certification of primary, secondary, and working standards. The standards should encompass a large area of the isotopic and chemical compositions of ma- terials widely used in the nuclear fuel cycle (UF6, metallic uranium or plutonium, mixtures of uranium and plutonium oxides, etc.). It is preferable, in the opinion of the experts, that the efforts of enterprises, IAEA member-states, and the IAEA in preparing secondary and working standards should be combined. The enter- prise provides material of appropriate quality and prepares a standard on the basis of this material, the state certifies the standard and issues a certificate, and the IAEA measures and verifies the characteristics of the standard. The third section discusses the goals and strategy of the use of standards, factors which affect the strat- egy, and the use of the standards in concrete situations. The principal factors determining the strategy of the Translated from Atomnaya Anergiya, Vol. 44, No.5, pp. 471-472, May, 1978. 548 0038-531X/78/4405-0548$07.50 ?1978 Plenum Publishing Corporation Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 use of physical standards are: 1) the necessary IAEA staff participating in the work on the given problem; 2) the cost of preparation, storage, and transportation of the standard; 3) transportation; 4) verification and pres- ervation of its authenticity; 5) the effect of the use of standards on the degree of reliability in the results of measurements. Depending on the situation, the effect of each factor on the choice of strategy will be different. In the opinion of the experts, however, the mcet applicable solution consists of a small number of primary or secondary standards being stored in the IAEA whereas the inspecting enterprises would have standards which would be verified with IAEA standards or calibrated in IAEA apparatus. The fourth section considers methods of calibrating apparatus as well as reducing errors of measure- ment stemming from the difference between sample and standard. To reduce these errors, in the opinion of the experts, it is advisable to create apparatus with a low sensitivity to parameters (differences in chemical composition, dimensions, matrices, etc.) which are not a measured quantity or apparatus which automatically makes correction dependent upon the difference. To date considerable experience has been acquired in the development of such apparatus. Built-in or pocket microcomputers are used to process the results of mea- surements in inspection practice. The need for higher speed and accuracy in carrying out inspections necessi- tates the use of available miniature computing technique as well as the development of special-purpose micro- computers. ALL-UNION SEMINAR ON THE PROCESSING OF PHYSICAL INFORMATION 0. P. Fedotov The seminar, the second, was held in Erevan in September 1977, with the participation of representa- tives of 20 institutes of the Soviet Union, the Joint Institute for Nuclear Research, CERN, and some institutes of Hungary, the German Democratic Republic, Great Britian, and Italy. The subject matter of the seminar covered practically all of the principal aspects of automation of scientific research. Considerable attention was paid to the introduction of computational networks in experimental physics, system software and specialized programming languages, and methods of calculation and optimization of mea- suring and computing complexes. The papers reflected the modernization of computers, the provision of com- puters with a large memory for accumulation of experimental data, and standardized interfaces for peripherals. Interesting data about these subjects were presented in papers by N. N. Govorun et al. (JINR), G. Davis (Gt. Britain), B. Tayler (CERN), B. M. Bobenko et al. (Institute of Theoretical and Experimental Physics ITEF), A. I. Bagin et al. (Radiotechnical Institute of the Academy of Sciences of the USSR), S. Z. Abelyan et al. (Ere- van Physics Institute), and others. A separate session was devoted to the representation of information and active man?computer interaction. Papers by A. V. Ekimov (Institute of High-Energy Physics IFVE), N. A. Abramov et al. (Radiotechnical Institute), A. S. Grui et al. (JINR), and V. B. Anikeev et al. (IFVE) pointed out the broad capabilities of graphical and textual displays, interesting designs of displays based on a color TV, cathode-ray storage tubes, etc. All of this work is especially important at the present time in view of the need to increase the capacity of computing technique by optimizing computing systems and developing systems for collective use. Other topics which were also taken up extensively in papers included the development of standardized program-controlled electronics and its use to create various automated systems for data acquisition and con- trol with the aid of computers. Most experimental facilities today employ standardized electronics built accord- ing to CAMAC logic and electrical standards. Papers by workers of IFVE, JINR, Institute of Nuclear Physics of the Siberian Branch of the Academy of Sciences of the USSR (IYaF SO AN SSSR), ITEF, etc., presented con- crete systems for counting information from wire chambers, complexes of apparatus for automation of experi- ments, including automation of accelerator monitoring and control. Programmed control with CA MAC systems was also considered. Some papers were devoted to a new line of development in CA MAC systems which has recently come into being and has gained widespread recognition. This concerns the development of "intellec- tual" CA MAC and electronic systems with autonomous "self-control" based on the application of micropro- cessors (papers by S. Szamori, Hungary; E. M. Gleibman et al., JINR; etc.). Translated from Atomnaya Energiya, Vol. 44, No.5, pp. 472-473, May, 1978. 0038-531X/78/4405-0549$07.50 01978 Plenum Publishing Corporation Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 549 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Considerable attention at the seminar was devoted to the development of measuring systems and new methods of measuring filmed information from a physics experiment. It was with great interest that the participants heard papers on the construction of new scanners based on cathode-ray tubes (JINR), on a system for the control of laser beam intensity (Moscow Engineering Physics Institute MIFI), on a system of auto- mated stereoprojectors (ITEF), on new units and modules of measuring apparatus (JINR), on a method of cali- brating automatic measuring machines (IFVE), etc. Notwithstanding the considerable advances made in the construction of measuring systems, these topics continue to be of interest to specialists owing to the continual emergence of new problems in the processing of film data. Many papers at the seminar were devoted to the mathematical treatment of measured information and especially to the automatic data indentification and filtration. There were reports on programs for on-line filtration in an HPD (JINR), filtration on a small computer in a system of PSP-2 automata (ITEF), off-line filtration in a Spiral Reader system (IFVE), on the method of analysis of the results of data processing in an interactive mode (JINR), etc. Considerable interest was aroused by a communication from the ITEF and CNAF (Italy) on the develop- ment of means for the high-speed realization of processing algorithms by apparatus and the creation, on this basis, of a system for automatic trajectory-data recognition in a "minimum reading" mode from the human side. Instrumental methods of recognition and filtration makes it possible for processing algorithms to be realized tens and hundreds of times more quickly than in present-day computers. A distinctive feature of the seminar was the fact that it paid particular attention to methods and means of automation developed in experimental physics , in other areas of scientific research, and for applied pur- poses. Two decades of development of automation of physics experiments have yielded a wealth of experience in creating processing methods and systems of unique accuracy and speed; many of them have proved to be ex- tremely effective for application in other areas of science and technology. It was noted that these methods and means have been applied in medicobiological research (papers by Erevan Physics Institute and IFVE), in pro- cessing flight data (MIFI), processing of stereo photographs and many other forms of half-tone graphical in- formation in geodesy, astronomy, etc. Measuring and computing technique has come into widespread use for the production and diagnostics of electronic apparatus and other applied purposes. The seminar took great interest in the review papers presented (R. Pose, German Democratic Republic; D. Wiscott, CERN; V. M. Kotov et al., JINR; V. L. Mamaev et al., MIFI; etc.). The seminar demonstrated the substantially increased level of research and development in the realm of automation of scientific experiments, more technical equipment in Soviet institutes, and considerable successes in the application of methods and means used in the automation of physics experiments to other research and to the solution of applied problems. The seminar was useful and furthered the exchange of information and coordination of efforts by various institutes in work on the automation of scientific experiment. The considerable organizational work done by workers of the Erevan Physics Institute contributed to a substantial degree to the success of the seminar. 550 The seminar proceedings will be published in 1978. Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 INTERNATIONAL CONGRESS ON CONCENTRATION OF USEFUL MINERALS I. P. Kondakov The Twelfth Congress, with the participation of 550 scientists from 41 countries, was held in Sao Paulo, Brazil, in August-September 1977. At 10 plenary sessions the Congress discussed 47 papers. The technology for processing raw materials difficult to concentrate was considered at three seminars. The theory and practice of the process of preparing crude ore and concentrating it by magnetic, iota- tion, and other methods were reflected at the Congress and it was noted that there was a trend toward increas- ing the use of hydrometallurgical methods of ore dressing. In the domain of ore preparation attention should be drawn to a communication on a unique method of auto- matic monitoring of wet grinding on the basis of measurements of the viscosity of the pulp (Australia), on the effect of chemical additives on grinding (U.S.A.), and on new approach by Italian specialists to screening which makes it possible to determine the principal kinetic parameters of the process for designing equipment or predicting the results of the process. An interesting cylindrical apparatus may find application in the atomic industry for separating fine classes of complex phosphate ores in heavy suspensions. In the opinion of the U.S. manufacturer, this appa- ratus has an advantage in comparison with a similar process in hydrocyclones. A laser photometric separator for ore sorting (U. S. A.), in operation in industry, was demonstrated dur- ing one paper and at the exhibition. Elements of its construction could be used to improve domestic radio- metric separators. Papers which described the application of magnetohydrostatic separation are worthy of mention. The most interesting of the new designs of separators with an intense magnetic field is a polygradient separator of the carousel type with a throughput of up to 400 tons/h with a higher field strength than in Jones separators (a joint U.S. development). _ In the area of flotation the Congress devoted much attention to the study of the physicochemical pro- cesses on the surface of minerals and the structure of flotation reagents on the basis of thermodynamic, elec- trochemical, and other modern methods of research employing computers. Some papers dealt with improve- ments in selective flotation processes by the addition of reagents (Sweden) as well as by vibroacoustical treat- ment (Bulgaria) and discussed the results obtained in the U.S.A. and Canada by introducing this process for hematite slurries. Considerable interest was awakened by a paper on the effective introduction of flotation machines of the OK-16 type with a chamber volume of up to 16 M3 in ore-dressing plants in Finland. A considerable proportion of the papers was devoted to combined ore dressing flowsheets including leach- ing, chemical and electrochemical deposition, sorption, and extraction, in addition to the traditional pyro- metallurgical methods. Some papers considered heap and underground leaching of oxidized copper, uranium, and other types of ore which are abundant in the U.S.A., Canada, Mexico, and Latin American countries. West German scientists reported the successful combination of grinding, leaching, and deposition of cop- per in a vibrating mill with subsequent flotation which increases the copper extraction from the ore in com- parison with the usual multistage flowsheet. Of the papers on process automation and control mention should be made of the introduction of the Pros- kon-103 system with a Courier-300 x-ray analyzer for controlling flotation in ore-dressing plants (Finland), the analysis, simulation, and optimization of large capacity mills, as well as grinding and flotation (Australia) and the control of iron-ore-dressing plants in Brazil. Some papers told of the achievements of Swedish, Finnish, and British companies in constructing and applying monitoring control equipment in iron-ore dressing and pel- letizing: measurement of the moisture content from the reflectivity, determination of the iron content in ores Translated from Atomnaya Energiya, Vol. 44, No. 5, pp. 473-474, May, 1978. 0038-531X/78/4405-0551 $ 07.50 ?1978 Plenum Publishing Corporation Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 551 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 and concentrates by radioactive methods, and a capacitive method of continuously determining the hematite content and an induction method of measuring the magnetite content on a conveyor, both methods being appli- cable for other forms of raw material. In the area of design, some interest was aroused by a paper on the development of large conveyor sys- tems in Brazil for the transportation of ore over distances of several kilometers at the rate of up to 16,000 tons/h per conveyor (belt width 1500-2200 mm, speed of travel 3-4 m/sec) and a paper on the "radial" (mono- block) principle of composing structures and construction of ore-dressing plants ensuring two to three times the throughput achieved with a "linear" arrangement while providing an enhanced coefficient of plant utiliza- tion. Some papers at the Congress were devoted to environmental protection. A noteworthy method was pre- sented for purification eliminating chromium and cyanide from effluents by a settling-flotation technique and for processing the waste from hydrometallurgical production of zinc; by this method valuable incidental com- ponents are extracted and contamination of the atmospheric and aqueous environment is prevented (Japan). In- teresting studies were made on the development of flowsheets for a closed circulating water supply for ore- dressing plants (Italy, Rumania, etc.). Some of these measures are being studied with a view to their applica- tion in the atomic industry. Certain attention was paid by the Congress organizers and delegates to a seminar on dressing of phos- phate raw material which frequently constitutes uranium?phosphorus ores. Papers were presented on the study of the types of ore, their reserves, location, and geology, on the mineralogical nature of the samples tested, as well as on studies on ore dressing. Samples of varying composition of low-grade phosphate raw ma- terial were used to consider traditional methods of dressing (grinding, roughing, washing off, classification, de slurrying, and separation in heavy media) and new methods, including flotation, calculation with washing off with water and leaching reagents, and magnetic and electric separation in various combinations. During the visit to Brazilian enterprises, the Soviet delegation became acquainted with the approach to the development of deposits and to design. All the plants are intended to process considerable raw material reserves of quite a high grade and have a high throughput: 5-46 million tons/yr (iron-ore plants), 3-12 million tons/yr (phosphate plants), and 300,000 tons/yr (niobium plants). ? Noteworthy requirements are imposed on the design of reprocessing plants. Thus, the designing is pre- ceded by a careful study of the material composition of the ore in the deposits, determination of a rotational technology for processing the raw material, and development of a technological flowsheet (as a rule, protected by patent) in two or three years for a pilot plant, and testing of commercial specimens of new equipment. The integrated processing of raw materials is ensured by the existence of developed technology for the extraction of incidental components; otherwise, the design, construction and commissioning of an enterprise are envisaged alternately with storage of intermediate products or reservation of ore containing incidental components. An invariable condition is that the processing plants be as close as possible to the deposits, including the organization of preliminary crushing at the edge of the open-cut mine with subsequent transportation by con- veyor to the main site of the dressing plant. An obligatory element in the ore-dressing flowsheet is that of laminar blending of crushed phosphate ore (after preliminary crushing or before grinding) in open or closed heaps with a 3-4 day capacity, formed by layer-by-layer pulling by means of a system of conveyor belts and a distributing bogie. Ore blending is all the more important for complex uranium raw material. The ore is taken away by machines made by Robins (U.S.A.) or Salzburger (Federal Republic of Germany). The system of iron-ore blending is even more complex. It is important when designing to concentrate the main technologi- cal operations as much as possible and to place them in a monoblock, to organize a system of total intraplant water cycle by dehydrating the final products in large thickeners with smaller quantities of thickened waste in- to a settling pond with an earth dike, etc. The proceedings of the Congress are of considerable interest for specialists of the atomic industry who can obtain valuable information about the most recent achievements on other countries in the realm of the engi- neering and technology of ore dressing which has much in common with the initial stage of uranium ore treat- ment. The Congress proceedings (in Russian) as well as a set of catalogs of the exhibition can be studied at the Institute of Information on Nonferrous Metals (Tsvetmetinformatsiya), at 101 Prospekt Mira, Moscow. 552 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 MEETING OF IAEA CONSULTANTS ON THE CHOICE OF SITES FOR BURIAL OF RADIOACTIVE WASTES M. K. Pimenov As is well known, early in 1977 the International Atomic Energy Agency drew up a long-term (8-10 years) comprehensive program for the coordination of work by interested member-states of the Agency on the burial of radioactive waste in geological formations in the solid, liquid, and gaseous state. On the basis of the ex- perience acquired in the world in storing and burying radioactive waste in geological formations as well as on the basis of national programs elaborated, the program is intended to provide a number of handbooks and methodological instructions which would regulate safe buriaL The task of the meeting, which was held in November-December 1977, in Vienna, Austria, was to map out further directions and time for work on drawing up handbooks for determining the geological, geophysical, hydrogeological, geomechanical, and physicochemical studies necessary to establish the suitability of a site for burial of radioactive waste in continental rock. This refers to burial of high-activity waste, containing long- lived isotopes, in loose rock and in salt, clay, and crystalline formations. In the course of the discussion on the national programs on the burial of radioactive waste it was ascer- tained that practically nowhere (apart from the USSR) is there special legislation regulating the burial of radio- active waste in geological formations. At the same time, however, the U.S.A., France, and the Federal Re- public of Germany, e.g., do have legislation which spells out the conditions for the injection (pumping) of in- dustrial effluents into deep-lying permeable horizons of the earth's crust. Most of the consultants voiced the opinion that problems of the injection of radioactive gaseous waste into deep porous horizons of the earth's crust are not of top priority and may be considered at a later date. At the meeting the consultants adopted a final document which takes note of the urgency in preparing hand- books specifying the composition and methods of conducting investigations to establish the suitability of a site for burial of radioactive waste in continental rock and agreed that priority should be given to the preparation of three handbooks. The first concerns establishment of the suitability, of salt structures, crystalline rock, and clay deposits for burials of high-activity waste, the second deals with the geological structures and storage strata for burial of liquid radioactive waste in deep-lying permeable horizons of the earth's crust. The third handbook should establish the suitability of structures for the burial of radioactive waste by employing the hy- draulic fault of the stratum. All three handbooks will be ready in 1979. Translated from Atomnaya nergiya, Vol. 44, No. 5, pp. 474-475, May, 1978. 0038-531X/78/4405-0553$07.50 01978 Plenum Publishing Corporation 553 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 MEETING OF IAEA EXPERTS ON PROTECTION OF POPULATION IN MAJOR RADIATION ACCIDENT Yu. V. Sivintsev and V. A. Klimanov The meeting, which took place in Lisbon, Portugal, in October 1977, discussed the structure, contents, and text of a handbook on the preparation of measures for the event of a major radiation accident. Major is taken to mean an accident in a nuclear facility, e.g., in an atomic power plant, which results in the ejection of large quantities of radioactive substances beyond the limits of the forbidden zone and there is a danger of part of the population being affected. The new document deals not only with protection of the population, but rather more with a set of measures which can be undertaken outside the site of the nuclear facility in the event of a radiation accident, primarily in an atomic power plant. It was agreed that the IAEA plan of work will include the preparation of recommendations for the elaboration of measures to be taken on the site of the nuclear facility. The handbook consists of six parts. The first part discusses methods of analyzing the scale of the radia- tion accident and the possible consequences for the population of the adjacent territory. It points out that these problems must be studied carefully in advance as applicable to local conditions, type of facility, and scale of the accident. The document is based on the initial assumption that operation of an atomic power, plant with a rate of release which does not grow above the maximum permissible (MPR) is radiation-safe. To the extent that it was noticed that a considerable (but brief) increase in the power surge above the MPR does not entail any signi- ficant increase in the radiation risk for the population, the integrated concentrations will be low. Accordingly, no-additional measures outside the atomic power plant are needed. In cases when the rate of release exceeds the MPR for a long time and reaches the "investigation level" (according to the terminology of the latest rec- ommendations of the International Commission on Radiological Protection ICRP), additional information must be obtained about the activity and isotopic composition of the release. This makes it possible to estimate the concentration of radionuclides in objects of the external environment and the intake of these radiators into the htunan organism. If this intake for the critical group of the population is below the maximum annual intake (MAI), as fixed by the ICRP and domestic radiation safety standards, then the only action necessary outside the atomic power plant site is for reserve groups of the external dosimetry service to carry out functions ac- cording to an expanded program for monitoring objects of the environment. If the results of radiometric and spectrometric monitoring in an atomic power plant indicate that the rate of release significantly surpassed the investigation level and the intakes exceeded the MAI, then the "intervention level" must be employed. Above these values the population of the district adjacent to the power plant may be injured and property and objects of the environment may suffer damage; measures may thus be required to protect them from radiation overex- posure. The second part considers possible protective measures such as moving the population to shelters, pro- phylactic application of stable iodine, evacuation of the population, deactivation of the people, food, and water, and the attendant risk and cost. The protective measures should be taken with due account of their risk, time after the accident, and only provided that the radiation rise is reduced significantly. The document deepens and supplements the classification of measures into immediate (upon passage of a cloud of gaseous discharge), intermediate (days, weeks), and long-range (months, years). The third part is devoted to a discussion of the concept of intervention level and consideration of various factors which affect the choice of level. It was decided that intervention level should mean a predetermined radiation dose which, if received by the population in the territory adjacent to the nuclear installation, would not require any measures. Translated from Atomnaya Energiya, Vol. 44, No. 5, pp. 475-476, May, 1978. 554 0038-531X/78/4405-0554$07.50 ?1978 Plenum Publishing Corporation Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 In addition to radiobiological data, in establishing numerical values for intervention levels one must take account of the social and economic conditions, types of nuclear facilities, characteristics of the environment, and other factors. The experts therefore deemed it is advisable to recommend the same values for all coun- tries and supplemented the handbook with an appendix of examples of concrete values adopted in IAEA member- countries. However, bearing in mind that the intervention level differs considerably in the various countries and that unjustifiably low levels may hinder the development of nuclear power, the experts decided to take only the levels adopted in the USA, Gt. Britain, and the USSR for illustrative material in the appendix. The fourth part of the handbook discusses the characteristics for prior planning of protective measures. This planning includes analysis of the potential danger of a radiation accident in a concrete nuclear installation from the point of view of possible consequences for the population and environment, demarcation of the most "dangerous" areas in the adjacent district, and estimation .of possible resources which could be used to dimin- ish the consequences of an accident. The fifth part analyzes various restoring measures, recommended for the latter phase of the radiation accident when the situation in the nuclear facility itself has been partially normalized and there is no danger of any further release of radioactive products. The last, sixth, part discusses the responsibility of various organizations and their cooperation in making decisions and eliminating the consequences of a radiation accident. The IAEA plans to publish the handbooks in the first half of 1978. 555 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 IN THE INSTITUTES METHODS OF HIGH-ENERGY PLASMA TECHNOLOGY V. G. Padalka and V. T. Tolok Fundamental research carried out by the Kharkov Physicotechnical Institute of the Academy of Sciences of the Ukrainian SSR (FTI AN USSR) on the physics of high-temperature plasma in connection with the problem of controlled thermonuclear fusion has resulted in the creation of an applied field, viz., high-energy plasma technology, for the purpose of solving many problems of present-day technology. Metal-plasma accelerators based on a cathodic vacuum arc are extremely promising for application [1, 2]. The high current density in the cathode spots (1-10 MA/cm2) and the specific power released (10-100 MW/ cm2) cause intensive evaporation of the cathode and generation of a plasma stream consisting of products of cathode erosion. The degree of ionization is quite high (up to 80-100% for the plasma of high-melting-point metals) and doubly charged ions with an energy of about 100 eV constitute the great majority. The effect of vacuum-arc generation of high-speed plasma' streams permits an anomalously high ion current (up to 10 A or more, ?10% of the discharge current) to be obtained from these streams. The energy efficiency of plasma generation may reach 20-30% while the plasma condensate is deposited at a rate of up to 0.5 j1/min. The process of deposition of plasma condensates, which has been dubbed CLB (condensation of material in a vacuum from a plasma stream under ion bombardment of plasma condensate), occurs in the Bulat appara- tuses [3] (Fig. 1). The vacuum chamber of the apparatus is pumped down to a pressure ? 6.6.10-4 N/m2 by a diffusion pump with a pumping speed of 1000 liters/sec. The electric-arc plasma accelerator is powered from a rectifier with a steep volt?ampere characteristic (no-load voltage 60 V, operating current up to 300 A). The cathode may be made of any conducting material whereas the vacuum-chamber vessel is the anode. The prod- uct being worked has a negative potential (of several hundred volts to several kilovolts) applied to it to ensure extraction of ions from the plasma stream and imparting the necessary additional energy to them. To obtain chemical compounds (nitrides, carbides) an alloying gas is introduced into the chamber. Any cathode material Fig. 1. The Bulat-3 apparatus. Translated from Atomnaya Energiya, Vol. 44, No.5, pp. 476-478, May, 1978. 556 0038-531X/78/4405-0556$07.50 ?1978 Plenum Publishing Corporation Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Fig. 2. AVED-40/800 electric-arc machine. (tungsten, tantalum, molybdenum, niobium, graphite, and semiconductors) can be evaporated as a result of the high temperature of the cathode spot of the vacuum arc. The introduction of an alloying gas into the vacuum chamber and its ionization in the discharge permit plasma beams to? be produced with a controlled content of various ionic components. The ionic state of the substance near the surface of the sample is activated by the interaction reaction, thus making it possible to obtain coatings with excellent physicomechanical properties (extrahard, wear-resis- tant, etc.). Since they are formed directly from the ion beam, the coatings are subjected to ionic treatment over their entire thickness (in contrast to ionic alloying). The composition and energy of the ion beams formed from the plasma stream can be regulated to vary the phase composition, structure, and properties of the plas- ma coatings. The resultant coatings, consisting of the pure starting materials evaporated and their solid solu- tions, compounds, and heterogeneous alloys. Multilayered compositions have been produced with programmed variation of the content of various components. Accelerated high-density ion beams obtained from a plasma stream allow the surface of the sample to be cleaned very efficiently by sputtering. This is a distinctive feature of the plasma stream method. Similar adhe- sion cannot be ensured by any other existing method of applying coatings. One of the most important areas in which coatings obtained by vacuum condensation of plasma streams can be applied is that of producing wear-resistant layers of nitrides of high-melting-point metals (especially molybdenum and titanium). The phase composition of the coatings and the physicomechanical properties can be altered by varying the conditions of the experiment (pressure and composition of the alloying gases, ion current density and energy, substrate temperature). The materials obtained have high values of the deter- mining parameters. In the case of coatings based on molybdenum nitride it was found that the crystal lattice had a high nitrogen content, that the lattice was highly distorted, and that the microhardness was up to 3500 kg/mm2. The process makes it possible to achieve various modes of strengthening: solid-solution and disper- sion strengthening, and strengthening by forming heterogeneous laminar structure [4]. Tools made of hard alloys and high-speed and tool steels were strengthened by the application of coatings based on titanium and molybdenum nitrides. Laboratory and industrial tests of the strengthened tools were carried out in the treatment of structural steels and alloys, cast irons, and nonferrous metals. It was estab- lished that strengthened by the CIB method increases the wear resistance of the tools two- to eight-fold, de- pending on the type of material treated, the conditions of the treatment, and the material of the coating. The CIB method is being introduced into industry. Specialized production sections for strengthening cutting tools have been in operation in the Malyshev and GPZ-8 plants (Kharkov) since 1975 with Bulat-2 ma- chines. Other enterprises in the country have been provided with Bulat-3 machines. The annual economic effectiveness of the introduction of Bulat-3 in a large engineering plant runs to about 100,000 rubles. 557 Declassified and Approved For Release 2013/03/07 : CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 The conditions necessary for the formation of a diamond structure can be created by the condensation of a stream of carbon plasma on a substrate. Upon striking the substrate, the energetic ions produce a local pressure which reaches hundreds of kilobar and the thermal energy released locally may correspond to a temperature of several thousand degrees. If the heat is removed from these "hot" points by cooling the sub- strate, metastable crystal forms, including diamond forms, can be quenched to room temperature. For crys- tallization of a diamond structure to occur it is sufficient for the ions to have an energy of several tens of electron volts. Under optimal conditions of carbon plasma deposition the density is 2.9 g/cm2, the resistivity is 108 S2 ? cm, and the microhardness of the coating is 9.8.10" N/m2. The coating is a two-phase material consisting of amorphous carbon and finely dispersed graphite, which have a low hardness, and a crystalline intermediate form of carbon with a high hardness [5]. Stationary erosion accelerators of metal plasma developed by the Kharkov Physicotechnical Institute are being used successfully in sorption titanium pumps as a means of regenerating the getter. In this case active gases are sorbed by titanium deposited on the inner surface of the pump chamber, inert gases are pumped out by an oil vapor pump with a pumping speed of about 1-2% of that of the nitrogen sorption pump. The AVED-40/800 electric-arc machines (Fig. 2) built on this principle are used extensively to pump down technological vacuum equipment (vacuum metallurgy, electron-beam welding, and furnaces for annealing titanium alloys) [6]. The AVED-40/800 specifications: Pumping speed, 104 liters/sec: nitrogen hydrogen ? . ? . ... air . ? OOOO ? Specific capacity, liter ? Nim2. sec: 4 8 3 nitrogen ? ? ? ? ? ? 267 hydrogen ? . 4 Service life in continuous operation before replacement of titanium (depending on gas load), h .. 300-3000 Maximum titanium consumption, mg/sec . 10 Start-up pressure, N/m2 .. 1.3-13 Maximal residual pressure (with water cooling of condensation surface), N/m2 1.3 .10-5 The results of both the development and improvement of plasma technology and its use in industry demon- strate.that the application of plasma streams opens up braod possibilities for the solution of scientific and in- dustrial problems. It is quite justifiable to assume that this technology will become widespread in industry. LITERATURE CITED 1. A. I. Morozov, in: Plasma Accelerators [in Russian], Mashinostroenie, Moscow (1973), p.5. 2. A. M. Dorodnov, Industrial Plasma Equipment [in Russian], Izd? Mosk. Vyssh. Tekh? Uch. im. N. E. Baumana, Moscow (1976). 3. A. K. Kruglov, At. Energ., 40, 103 (1976). 4. A. A. Andreev et al., in: Proc. Third All-Union Conf. on Plasma Accelerators [in Russian], Izd. Inst. Fiz. Akati Nauk BSSR, Minsk (1976), p.218. 5. N. N. Matyushenko et al., Dokl. Akad. Nauk Ukr. SSR, Ser. A, No. 5, 460 (1976). 6. L. P. Sablev et al., Prib. Tekh. Eksp., No. 6, 230 (1976). 558 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 BOOK REVIEWS A. P. Shi-renko RADIOISOTOPIC METHODS OF MEASURING ALTITUDES* Reviewed by E. R. Kartashev In aircraft Iairplanes, helicopters, etc.) the altitude can be determined by radio altimeters which, how- ever, do not provide sufficient accuracy in low-altitude measurements (below 40-50 m). At the same time, exact knowledge of low altitudes is particularly important in such important stages of the flight as landing (especially under difficult meterological conditions and with poor visibility). Determination of high altitudes (tens of kilometers) is also an urgent problem. A promising method of determining both low and high altitudes, according to many researchers, is a radiation method based on measurement of the degree of back scattering or absorption of the radiation of various radioactive nuclides. The problems of measurement of altitides by the radiation method have not been sufficiently illuminated in the scientific and engineering literature. Hence the great interest in the book under review which considers the various aspects of this method on the basis of data from the literature and research done by the author. The book goes very deeply into the theoretical foundations of the radiation method of measuring aircraft altitudes from a fraction of a meter to 100 km. Particular attention is paid to substantiation of the possibility of determining flight altitude by using y radiation backscattered by the air and the underlying surface and ab- sorption of (3 radiation by the air. The author considers structural schemes, altitude characteristics of radiation altimeters, and the effect of various factors on the accuracy of their readings. He assesses the advantages and disadvantages of such altimeters, presents some recommendations on reduction of the-effect of possible disturbances and on the choice of radiation sources and detectors most suitable for use in radiation altimeters. The results of re- searches carried out by the author are of considerable -interest to specialists. The theoretical and experi- mental altitude characteristics, in particular, are in good agreement with allowance for the assumptions made for the calculations. The book under review, however, is not free of shortcomings. Evidently, it was not the author's under- taking to develop an on-board radiation altimeter. The models used in the experimental investigations were made up of standard instruments manufactured in preceding years and the separate units were based on radio tubes. Accordingly, the detailed description of this apparatus as well as other instruments used in the experi- ments was unnecessary since it is of no assistance to the designer with modern microelectronic techniques at his disposal nor is it needed by the experimenter who most often has access to a set of other instruments. Such descriptions only clutter up the text and draw attention away from a book that is interesting on the whole. *Atomizdat, Moscow (1977). Translated from Atomnaya Energiya, Vol. 44, No. 5, No. 5, 13. 478, May, 1978. 0038-531X/78/4405-0559$07.50 ?1978 Plenum Publishing Corporation Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 559 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 , from ,confULTAIIT/ BUREAU A ,nEw JOURnAL Programming and Computer Software A cover-to-cover translation of Programmirovanie Editor: N. N. Govorun This new journal provides authoritative and up-to-date reports on current ,progress in programming and the use of com- puters. By publishing papers ranging-from theoretical research to practical results, this bimonthly will be essential to a wide circle of specialists. It features results of vital research in the following directions: . - ? logical problems of programming; applied thebry of algorithms; and control of computational processes ? program organization; programming methods connected with the'idiosyncrasies of input languages, hardware, and problem classes; and parallel programming ? operating systems; programming systems; programmer aids; software systems; data-control systems: 10 systems; and subroutine'libraries. .Subscription: Volume 4, 1978 (6 issues) $95.00 Random Titles from this Journal PROGRAMMING THEO-AY Structure of an Information System?N. A. Krinitskii, V. N. Krihitskii, and D. A.' Stepanchenko The Active Set of Program Pages and Its Behavior?V. P. Kutepov, Estimate of the Efficiency of Replacement Algorithms?Yu. A. Stoyan PROGRAMMING METHODS Method and Algorithm for Checking Group Items in the Machine Processing of Economic Information?G. L. Livshin Parallelization of the Fast Fourier Transform Algorithm in Encephalogram Spectrum Analysis?V. S. MedoVyi and V. O. Trush COMPUTER SOFTWARE'AND SYSTEM PROGRAMMING Increasing the Efficiency of Object Programs by Changing the Initial Grammar of the Programming Language?S. Ya. Vilenkin and S. M. Movshovich A Metalanguage, a , Translation Scheme, and Syntactic Analysis in a -System for Constructing Highly Effective , Translators?M. I. Belyakov and L. G. Natenson Tabular. Information Output System?v. D. Prachenko, V. P. Semik, N. D. Tyutvina, 'and K. A. Chizhov Questions in the Creation of Software for Terminal Devices?V. A. Kitov ? 7 SEND FORFREE EXAMINATION COPY - In United Kingdom: PLENUM PUBLISHING'CORPORATION 227 West 17th Street, New York, N:Y. 10011 , ? Black Arrow House 2 Chandos Road, London NW10 6NR England Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2 NEW RUSSIAN JOURNALS IN ENGLISH TRANSLATION 'BIOLOGY BULLETIN. lzvestiya Alademii Nauk SSSR, Seriya Biologicheskaya, . The biological proceedings of the Academy of Sciences of the USSR, this prestigioUs new bimonthly presents the work of the leading academicians on eiery aspect of the life sciences?from micro- and molecular biology to zoology, physiology, and space medicine.; VOlume 5, 1978 (6 issues)' $175.00 SOVIET JOURNAL OF MARINE BIOLOGY Biologiya Morya Devoted solely to research on marine, organisms and their activity; practical considerations for their preservation, and reproduction of the biological resources of the seas and : oceans. -Volume 4, 1978 (6 issues) $95.00' WATER RESOURCES Vodnye Resursy Evaluates the water resources of specific geographicaliareas throughout the world and revi7ws regularities of water re- sources formation as well as scientific principles of their optimal use. Volume 5, 1978 (6 issues) $.190.00 HUMAN PHYSIOLOGY Fiziologiya Cheloveka A new, innovative journal retical and applied aspects physiology. , Volume 4, 1978 (6 issues) concerned exclusively with theo- of the expanding field Of human $175.00 SOVIET JOURNAL OF BIOORGANIC CHEMISTRY Bioorganicheskaya Khimiya Features articles on isolation and purification of naturally occurring, biologically active compounds; the establishment of their structure, methods of synthesis, and determination of the relation between 'structure and biological function. Volume 4, 1978 (12 issues) $225.00 ? . SOVIET JOURNAL OF COORDINATION CHEMISTRY Koordinatsionnaya Khimiya Describes the achievements of Modern theoretical and applied coordination chemistry. Topics include the syn- thesis and properties of new coordination, compounds; .reactions involving intraspheral substitution and,transforma- tion of ligands; complexes with polyfunctional and macro: molecular ligands complexing in solutions; and kinetics and mechanisms of reactions involving the participation' of coordination compounds. VOlume 4, 1978 (12-issues) .$235.00 THE SOVIET JOURNAL OF GLASS PHYSICS AND CHEMISTRY Fizika i Khimiya Stekla Devoted to current theoretical and applied 'research on three interlinked problems in glass technology; the nature of the chemical bonds in a vitrifying melt and in glass; the struc- ture-statistical -principle; and the macroscopic properties of glass. Volume 4, 1978 (6 issue!) $125.00 LITHUANIAN MATHEMATICAL JOURNAL '` Litovskii MatiMaticheskii Sbornik An international Medium for the rapid publication of the latest developments in mathematics, this quarterly keeps western scientists abreast 1of both practical and theoretical configurations. Among the many areas reported on in depth are the generalized Green's function, the Monte Carlo,Method, the "innovation theorem," and thtte Martin- gale problem. Volume 18, 1978 (4 issues) $150.00 , PROGRAMMING AND COMPUTER SOFTWARE ProgramMirovanie Reports-on current progress in programming and the use of computers. Topics covered include logical problems of programming; applied theory of algorithms; control of com- putational processes; program organization; programming methods connected with the idiosyncracies Of input, lan- guages, hardware, and problem classes; parallel programrn- ing; operating systems; programming systems; programmer aids; software systems; data-control systems; 10 systems; and subroutine libraries. Volume 4, 1978 (6 issues) ? : $95.00 SOVIET MICROELECTRONICS Mikroelektronika Reports on the latest advances in solutions of fundamental problems of microelectronics. Discusses new physical principles, materials, and methods for creating components, especially in large systems. Volume 7, 1978 (6 issues) $135.00 Send for Your Free Examination Copy PLENUM PUBLISHING _CORPORATION, 227 West 17th Street, New York, N.Y. 10011 In United Kingdom: Black Arrow House, 2 Chandos Road, London NW10 6NR, England Prices slightly higher, outside the U.S. Prices subject to change without notice. ? Declassified and Approved For Release 2013/03/07: CIA-RDP10-02196R000700110004-2
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