Alekseev, P. N.; Balanin, A. L.; Fomichenko, P. A.; Grishanin, E. I.; Ivanov, E. A.; Ponomarev, A. S.; Zakharko, Y. A.
American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)2006
American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)2006
AbstractAbstract
[en] The paper presents the status in elaboration of a reactor facility with a Gas Cooled Fast Reactor named BGR-1000 on the initial stage of developments. In the present time, general formulation of the concept is given and analysis of possible design decisions for the active core and first circuit equipment is performed. The design of a reactor facility with the fast helium cooled reactor 1000 MWe is based on the active core with fuel assemblies containing the fixed bed of coated fuel microparticles directly cooled by cross flow of helium coolant with moderate (750 deg. C) outlet temperature. The neutron-physics characteristics of this reactor and their connection with the parameters of the core layout and fuel cycle options are preliminary evaluated. Preliminary assessments are performed for thermal-hydraulic characteristics, fuel behavior analysis, etc. (authors)
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2006; 3 p; American Nuclear Society - ANS; La Grange Park (United States); PHYSOR-2006: American Nuclear Society's Topical Meeting on Reactor Physics - Advances in Nuclear Analysis and Simulation; Vancouver, BC (Canada); 10-14 Sep 2006; ISBN 0-89448-697-7; ; Country of input: France; 2 refs.
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Book
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Conference
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Nevinitsa, V. A.; Dudnikov, A. A.; Blandinskiy, V. Yu.; Balanin, A. L.; Alekseev, P. N.; Titarenko, Yu. E.; Batyaev, V. F.; Pavlov, K. V.; Titarenko, A. Yu., E-mail: Neviniza-VA@nrcki.ru, E-mail: yuri.titarenko@itep.ru2015
AbstractAbstract
[en] A subcritical molten salt reactor with an external neutron source is studied computationally as a facility for incineration and transmutation of minor actinides from spent nuclear fuel of reactors of VVER-1000 type and for producing "2"3"3U from "2"3"2Th. The reactor configuration is chosen, the requirements to be imposed on the external neutron source are formulated, and the equilibrium isotopic composition of heavy nuclides and the key parameters of the fuel cycle are calculated
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Copyright (c) 2015 Pleiades Publishing, Ltd.; Country of input: International Atomic Energy Agency (IAEA)
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Journal Article
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ACTINIDE NUCLEI, ALPHA DECAY RADIOISOTOPES, DIMENSIONLESS NUMBERS, ELEMENTS, ENERGY SOURCES, ENRICHED URANIUM REACTORS, EVEN-EVEN NUCLEI, EVEN-ODD NUCLEI, FUELS, HEAVY ION DECAY RADIOISOTOPES, HEAVY NUCLEI, ISOTOPES, MATERIALS, METALS, NEON 24 DECAY RADIOISOTOPES, NUCLEAR FUELS, NUCLEI, PARTICLE SOURCES, POWER REACTORS, PWR TYPE REACTORS, RADIATION SOURCES, RADIOISOTOPES, REACTOR MATERIALS, REACTORS, SPONTANEOUS FISSION RADIOISOTOPES, THERMAL REACTORS, THORIUM ISOTOPES, URANIUM ISOTOPES, WATER COOLED REACTORS, WATER MODERATED REACTORS, YEARS LIVING RADIOISOTOPES
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Balanin, A. L.; Boyarinov, V. F.; Glushkov, E. S.; Zimin, A. A.; Kompaniets, G. V.; Nevinitsa, V. A.; Moroz, N. P.; Fomichenko, P. A.; Timoshinov, A. V.; Volkov, Yu. N., E-mail: Neviniza-VA@nrcki.ru2016
AbstractAbstract
[en] The application of experimental information on measured axial distributions of fission reaction rates for development of 3D numerical models of the ASTRA critical facility taking into account azimuthal asymmetry of the assembly simulating a HTGR with annular core is substantiated. Owing to the presence of the bottom reflector and the absence of the top reflector, the application of 2D models based on experimentally determined buckling is impossible for calculation of critical assemblies of the ASTRA facility; therefore, an alternative approach based on the application of the extrapolated assembly height is proposed. This approach is exemplified by the numerical analysis of experiments on measurement of efficiency of control rods mockups and protection system (CPS).
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Copyright (c) 2016 Pleiades Publishing, Ltd.; Country of input: International Atomic Energy Agency (IAEA)
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Journal Article
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Numerical Data
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