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Your search keyword '"Yu. M. Bulkin"' showing total 14 results
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14 results on '"Yu. M. Bulkin"'

1. Use of nuclear reactors for centralized heat supply and central heating

Author

B. B. Baturov, G. A. Zvereva, Yu. M. Bulkin, I. V. Galaktionov, Yu. I. Tokarev, L. A. Melent'ev, E. S. Smirnova, and V. A. Chernyaev

Subjects
Nuclear meltdown, Nuclear Energy and Engineering, Nuclear reactor core, Nuclear engineering, General Engineering, Heat supply, Environmental science, Nuclear reactor safety systems
Published
1977

2. Development and use of the IVV-2M fuel assembly

Author

V. E. Pivovarov, I. A. Stenbok, V. I. Zelenov, Yu. A. Safin, S. G. Karpechko, V. D. Zaboikin, Yu. M. Bulkin, V. G. Aden, E. F. Kartashev, A. G. Sila-Novitskii, V. I. Uvarov, I. Ya. Emel'yanov, A. D. Nikiforov, Ya. D. Pakhomov, A. S. Terekhov, and V. I. Vasenkov

Subjects
Materials science, Nuclear engineering, Uranium dioxide, General Engineering, Solid fuel, Neutron temperature, Nuclear physics, Condensed Matter::Materials Science, chemistry.chemical_compound, Nuclear Energy and Engineering, Nuclear reactor core, chemistry, Neutron flux, visual_art, Aluminium alloy, visual_art.visual_art_medium, Research reactor, Physics::Chemical Physics, Burnup
Abstract

The design and performance of a fuel assembly, intended for use in the water cooled and moderated IVV-2M research reactor and consisting of dioxide dispersed in an aluminium alloy matrix encased in an aluminium alloy can, is presented. Experimental and theoretical studies included neutron characteristics of the reactor core, thermohydraulic behavior, and thermal neutron flux distribution. Data are also presented on the specific charge in u 235, the metal to water volume ratio, the specific heat removal surface, and maximum power of the assembly.

Published
1986

3. Physical start-up of IBR-2 pulsed research reactor

Author

Yu. S. Yazvitskii, N. A. Khryastov, V. A. Arkhipov, Yu. I. Mityaev, V. V. Melikhov, E. P. Shabalin, L. V. Edunov, V. D. Anan'ev, A. D. Rogov, D.I. Blokhintsev, V. S. Lavrukhin, A. I. Babaev, V. P. Plastinin, E. D. Vorob'ev, V. L. Lomidze, Yu. M. Bulkin, N. A. Dollezhal, V. S. Smirnov, Yu. N. Pepelyshev, I. M. Frank, and B. N. Bunin

Subjects
Materials science, Nuclear Energy and Engineering, Nuclear engineering, General Engineering, Research reactor, Start up
Published
1979

4. Physical and power startup of the first unit of the V. I. Lenin Nuclear Power Station, Leningrad

Author

A. Ya. Kramerov, A P Aleksandrov, I. Ya. Emel'yanov, S. P. Kuznetsov, A. A. Kubrochenko, A. G. Meshkov, Yu. M. Bulkin, I. D. Dmitriev, N. A. Dollezhal, A. P. Sirotkin, A. P. Eperin, S. M. Feinberg, A. F. Epifanov, E. V. Kulov, E. P. Kunegin, K. K. Polushkin, V. I. Ryabov, and L. V. Konstantinov

Subjects
Nuclear Energy and Engineering, business.industry, Nuclear engineering, General Engineering, Environmental science, Nuclear power, business, Unit (housing), Power (physics)
Published
1974

5. High-temperature power-technological reactor with solid coolant and radiative heat exchange

Author

I. L. Chikhladze, Yu. M. Bulkin, Yu. I. Koryakin, S. V. Radchenko, V. P. Smirnov, V. A. Chernyaev, A. V. Petrushin, E. S. Gerasimov, I. Ya. Emel'yanov, A. M. Alekseev, S. I. Vasil'ev, N. D. Zaichko, É. K. Nazarov, and N. A. Dollezhal

Subjects
Materials science, Nuclear Energy and Engineering, Nuclear engineering, Heat transfer, Heat spreader, Heat exchanger, General Engineering, Micro heat exchanger, Plate heat exchanger, Heat sink, Copper in heat exchangers, Coolant
Published
1984

6. Power startup of the IBR-2 reactor and the first physics investigations in its beams

Author

V. I. Dushchikov, E. P. Shabalin, Yu. M. Bulkin, V. D. Anan'ev, Yu. M. Cherkashov, V. A. Arkhipov, A. I. Babaev, L. V. Edunov, B. N. Bunin, Yu. I. Mityaev, V. S. Dmitriev, Yu. N. Pepelysnev, V. L. Lomidze, N. A. Khryastov, A. D. Zhirnov, N. A. Dollezhal, V. S. Smirnov, Yu. S. Yazvitskii, I. M. Frank, and Yu.M. Ostanevich

Subjects
Physics, Nuclear Energy and Engineering, Nuclear engineering, General Engineering, Power (physics)
Published
1984

8. Physical and operating characteristics of the SM-2 reactor

Author

V. M. Gryazev, S. M. Feinberg, V. I. Ageenkov, P. G. Aver'yanov, I. Ya. Emel'yanov, A. S. Kochenov, V. A. Tsykanov, N. A. Dollezhal, E. D. Vorob'ev, and Yu. M. Bulkin

Subjects
Correctness, Nuclear Energy and Engineering, Computer science, Nuclear engineering, General Engineering, ComputerApplications_COMPUTERSINOTHERSYSTEMS
Abstract

Operating experience with the SM-2 reactor verified the correctness of the basic physical and engineering ideas incorporated in the design

Published
1964

9. The 50-megawatt SM research reactor

Author

A. G. Samoilov, S. T. Konobeevskii, O. L. Shchipakin, V. P. Perfil'ev, S. M. Feinberg, A. G. Filippov, V. I. Ageenkov, I. Ya. Emel'yanov, Yu. M. Bulkin, V. A. Tsykanov, A. D. Zhirnov, and N. A. Dollezhal

Subjects
Nuclear physics, Physics, Flux (metallurgy), Nuclear Energy and Engineering, Neutron flux, Astrophysics::High Energy Astrophysical Phenomena, Research reactor, Neutron, Physics::Chemical Physics, High ratio
Abstract

The present article describes the design of the Soviet SM research reactor, where the neutral flux attains 2.2·1015 neutron/cm2-sec. The intensive neutron and γ-ray fluxes that are obtained in the reactor make it possible to perform many investigations in the fields of nuclear physics and reactor techniques.

Published
1961

10. Design characteristics and optimization of the reactivity modulator in the IBR-2 reactor

Author

A. I. Khoperskii, I. M. Frank, V. I. Sokolov, V. P. Zinov'ev, E.N. Volkov, A. K. Popov, N. A. Khryastov, V.V. Bondarenko, G. N. Zhemchuzhnikov, F. I. Ukraintsev, Yu. S. Yazvitskii, Yu. M. Bulkin, B. I. Kuprin, V. S. Smirnov, V. S. Lobanov, E. P. Shabalin, V. D. Anan'ev, and D.I. Blokhintsev

Subjects
Materials science, Nuclear Energy and Engineering, General Engineering, Reactivity (chemistry), Combinatorial chemistry, Design characteristics
Published
1971

11. The 50 mw research reactor SM

Author

S. T. Konobeevskii, Yu. M. Bulkin, I.Y. Emel'ianov, O. L. Shchipakin, V. P. Perfil'ev, A. D. Zhirnov, S. M. Feinberg, N. A. Dollezhal, A. G. Samoilov, V.A. Tsikanov, A. G. Filippov, and V. I. Ageenkov

Subjects
Nuclear physics, Physics, Nuclear reactor core, Neutron flux, law, General Engineering, Thermal power station, Research reactor, Neutron, Nuclear reactor, Neutron moderator, Liquid fluoride thorium reactor, law.invention
Abstract

Design details are given for the Soviet research reactor SM in which the neutron flux reaches a level of 2·2 × 10 15 neutrons cm −2 sec −1 . The intense fluxes of neutrons and γ-rays available in this reactor enable a large number of experiments in the fields of nuclear physics and reactor technology to be carried out. The SM reactor is an intermediate reactor with a high ratio of maximum neutron flux to thermal power. The efficiency of any research reactor is determined by the value of this ratio and for the SM reactor it is 4·4 × 10 10 neutrons cm −2 sec −1 kW −1 . The building of this reactor represents a notable advance in Soviet reactor construction and its design owes much to the experience gained in designing and running earlier Soviet research reactors. Since this article is concerned mainly with the engineering aspects of the design, no details are given of the physical characteristics of the reactor.

Published
1962

12. The Leningrad nuclear power station and the outlook for channel type BWR'S

Author

A. D. Zhirnov, S. P. Kuznetsov, V. S. Romanenko, I. Ya. Emel'yanov, N. A. Dollezhal, A. P. Aleksandrov, O. M. Glazkov, A. M. Petros'yants, K. K. Polushkin, A. K. Kalugin, V. M. Fedulenko, E. P. Kunegin, S. M. Feinberg, A. P. Sirotkin, A. Ya. Kramerov, Yu. M. Bulkin, and V. A. Chebotarev

Subjects
Physics, Nuclear Energy and Engineering, business.industry, Nuclear engineering, General Engineering, Channel (broadcasting), Nuclear power, business
Published
1971

13. The RG-1 geological research reactor

Author

L. V. Konstantinov, Yu. M. Bulkin, A. D. Zhirnov, I. A. Stenbok, A. M. Benevolenskii, V. A. Nikolaev, and V. S. Lobanov

Subjects
Pool-type reactor, Nuclear Energy and Engineering, business.industry, Nuclear engineering, General Engineering, Environmental science, Research reactor, Process engineering, business
Published
1966

14. The CO-1 neutron booster

Author

V. A. Nikolaev, B. S. Poppel, Yu. M. Bulkin, L. V. Konstantinov, I. Kh. Ganev, A. D. Zhirnov, and V. S. Lobanov

Subjects
Nuclear physics, Materials science, Nuclear Energy and Engineering, Booster (electric power), General Engineering, Neutron
Published
1966

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