Physical characteristics of the BN-600 reactor

Kazanskii, Yu. A.; Troyanov, Marc; Matveev, V. I.; Evseev, A. Ya.; Zvonarev, A. V.; Kiryushin, A. I.; Vasil’ev, B. A.; Belov, S. P.; Matveenko, I. P.; Kulabukhov, Yu.S.; Chernyi, V. A.; Dvukhsherstnov, V. G.; Bakov, A. T.; Ivanov, A. P.; Tyutyunnikov, P. L.; Pshakin, G.M.

doi:10.1007/bf01126679

At Energy

1983

DOI: 10.1007/bf01126679

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Physical characteristics of the BN-600 reactor

Yu. A. Kazanskii¹,

Marc Troyanov²,

V. I. Matveev³

et al.

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1986

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Cited by 7 publications

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“…The fuel-assembly designs, the arrangement of the core and the cartogram of the BN-VT load are similar to those of BN-600 [3]. The BN-VT core consists of a collection of assemblies -fuel assemblies, control and safety rods, neutron sources, steel protection assemblies and boron protection assemblies arranged along a triangular lattice with average spacing 98.35 mm.…”

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confidence: 98%

High-Temperature Nuclear Energy Technology Based on Sodium-Cooled Fast Reactors for Hydrogen Production

et al. 2014

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Studies show that in principle it is possible by relying on the BN-600 design to secure the required parameters of a reactor setup with a fast reactor with high-temperature sodium coolant (BN-VT) for hydrogen production. The calculations for 600 MW(t) BN-VT for electricity and hydrogen production based on solid-oxide electrolysis of water taking account of a fundamentally different method of purificationremoval of hydrogen and tritium from the sodium by vacuum pumping through special membranes -have shown that the efficiency of such a system is ~40% and hydrogen production volume is 2.8·10 4 liters/sec. The purification of hydrogen by removing tritium to a concentration ensuring the maximum admissible hydrogen concentration in the hydrogen produced 3.26 Bq/liter, imposes additional requirements on the hydrogen removal system.The most important problem determining the future development of environmentally clean power generation is bringing hydrogen into the fuel cycle. Hydrogen is an attractive element for replacing fossil fuels (oil, gas), though it is not a source but rather a carrier of energy. As expected, the demand for hydrogen production is increasing rapidly. At the present time, the main method of hydrogen production is steam conversion of methane. However, from the standpoint of the longterm future of the large-scale production of hydrogen this method is not viable because it requires the use of nonrenewable resources and is accompanied by the release of greenhouse gases. For this reason, alternative methods of hydrogen production by splitting water using thermochemical or electrolytic heat sources are being developed.At present, the best developed high-temperature sources of heat could be Gen-IV nuclear reactors because the proposed heat carriers are gases, liquid metals (sodium, lead) and fused salts. The temperature at the exit from the core in these reactors can reach 900-950°C. They represent a new class of reactors intended for electricity production with high efficiency (50%) and supporting important technological processes in hydrogen production, coal gasification and liquefaction, deep reprocessing of oil, conversion of biomass into liquid fuel as well as in the chemical industry and metallurgy.The conceptual studies performed at the Leipunskii Institute for Physics and Power Engineering (FEI) on the development of a high-energy high-temperature fast sodium reactor (BN-VT) show that the development of such a reactor is technically feasible [1]. The technological problems associated with the high temperature in the reactor setup are paramount. In the present work, a great deal of attention is given to validating the development of a system that secures the quality of the sodium coolant at high temperature and the hydrogen concentration for a long service life, heat-and radiation-resistant hightemperature construction materials and their corrosion resistance with oxygen content in the sodium coolant at the level 0.1 ppm. Concrete estimates were made for 600 MW(t) BN-VT.

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High-Temperature Nuclear Energy Technology Based on Sodium-Cooled Fast Reactors for Hydrogen Production

et al. 2014

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“…The extrapolated minimum critical mass was 215 fuel assemblies of the high-and 36 ± 1 fuel assemblies of the low-enrichment zones [2].…”

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“…Since the neutron flux from this source at the location of the sensors is approximately 100 times less than the flux from a photoneutron source, the standard control-measurement apparatus did not give the required sensitivity. For this reason, an additional complex of startup apparatus with six detector blocks was developed for physical startup: three with KNT-56 cameras (current channels) and three with SNM-18, -14 neutron sensors [2].…”

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Main stages of physical startup of BN-600 and comparison of the measured and nominal characteristics

et al. 2010

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A retrospective exposition of the preparation for and performance of the physical startup of BN-600 is presented. There are three sections: program of physical startup and measurements of the physical characteristics, physical startup procedure, and main results of the investigations of the neutron-physical characteristics of a reactor and their comparison with the nominal characteristics. The use of the experience gained in performing the physical startup of BN-600 will be important for the startup of other advanced fast reactors, first and foremost, BN-800.The sodium-cooled fast power reactor BN-600 was put into operation in the Beloyarskaya nuclear power plant on April 8, 1980 [1]. Since starting operation, it has produced ~112·10 9 kW·h of electricity with calendar time utilization factor 77% and installed capacity utilization factor 72%. For the nominal 80%, the maximum installed capacity utilization factor 83.5% was attained in 1992. The construction of the reactor was completed at the end of 1979. Physical startup was begun on December 28. The reactor first reached a critical state with minimum critical mass on February 26, 1980. Successful startup of BN-600 was largely determined by high quality of the design, including validation of the neutron-physical characteristics.The present article gives a retrospective exposition of the main stages of the preparation and physical startup of BN-600 and compares with the nominal characteristics of the reactor as determined at startup. The overall management of the preparations for and physical startup of BN-600 was handled by V. P. NevskiiIndustrial Association Soyuzatomenergo, A. G. Meshkov, E. V. Kulov, and A. M. Smirnov -16th Chief Direactorate of the Ministry of Medium Machine Building, O. D. Kazachkovskii, M. F. Troyanov, and Yu. A. Kazanskii -Physics and Power Engineering Institute (FEI), F. M. Mitenkov, V. I. Shiryaev, O. B. Samoilov, V. V. Pakhomov -Afrikantov OKBM, and V. M. Malyshev, V. I. Kupnyi, and A. Ya. Evseev -Beloyarskaya Nuclear Power Plant. A group of specialists directly managed the preparation and physical startup and investigations of the characteristics of BN-600: Yu. A. Kazanskii -Scientific Direactor, A. Ya, Evseev -Deputy Scientific Direactor, V. I. Matveev, A. V. Zvonarev, A. A. Vaimugin, B. A. Vasiliev, and Yu. A. Lebedev -members of the group.

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Reliability of calculation of the energy-liberation field in a fast reactor

Voropaev¹,

Vankov²,

Zinin³

et al. 1989

At Energy

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Physical characteristics of the BN-600 reactor

Cited by 7 publications

References 1 publication

High-Temperature Nuclear Energy Technology Based on Sodium-Cooled Fast Reactors for Hydrogen Production

High-Temperature Nuclear Energy Technology Based on Sodium-Cooled Fast Reactors for Hydrogen Production

Main stages of physical startup of BN-600 and comparison of the measured and nominal characteristics

Reliability of calculation of the energy-liberation field in a fast reactor

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