Abstract
The problems of improving the safety of the existed NPPs with fast-neutron reactors (BN-600) and those under construction (BN-800), as well as the projects of fast-neutron reactors of new generation with an advanced level of inherent safety are considered.
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References
V. M. Poplavskii, “Fast Reactors. State-of-the-Art and Prospects,” Atomnaya Energiya 96(5), 327–335 (2004).
“Status of Liquid Metal Cooled Fast Reactor Technology,” IAEA-TCDOC-L083 (IAEA, Vienna, 1999).
V. M. Mourogov, P. E. Juhn, J. Kupitz, and A. A. Rineiskii, “Liquid-Metal-Cooled Fast Reactor (LMFR). Development and IAEA Activities,” Energie 23(7/8), 637–648 (1998).
F. M. Mitenkov, “Prospects of Development of Fast-Neutron Reactors,” Atomnaya Energiya 92(6), 423–432 (2002).
A. A. Rineiskii, V. B. Lytkin, and V. S. Kagramanian, “Commercialization of Fast Reactors,” in Proceedings of International Conference on Fast Reactors and Related Fuel Cycles, Kyoto, Japan, Oct. 28–Nov. 1 1991, 18.7-1.
A. A. Rineiskii, “Comparison of Technical and Economical Characteristics of Modern Reactors with Thermal and Fast Neutrons,” Atomnaya Energiya 53(6), 360–367 (1982).
E. O. Adamov, et al., “Self-Consistent Model of Development of Nuclear Power Engineering and Its Fuel Cycle,” Atomnaya Energiya 86(5), 361–370 (1999).
V. M. Poplavskii, A. M. Tsibulya, A. A. Kamaev, et al., “Promising Sodium Cooled BN-1800 Fast Reactor That Meets the Requirements of Nuclear Power Engineering of XXI [roman] Century,” Atomnaya Energiya 96(5), 335–342 (2004).
V. I. Matveev, V. A. Eliseev, and I. V. Malysheva, “A Choice of Main Parameters and Characteristics of Promising Fast Reactor with Sodium Coolant for Power Engineeing,” in Selected Papers of Physical and Energy Institute, Ed. by A. V. Zrodnikov (GNTs RF-FEI, Obninsk, 2000).
Yu. E. Bagdaearov et al., Engineering Problems of Fast-Neutron Reactors (Atomizdat, Moscow, 1969).
G. B. Usynin and E. B. Kusmartsev, Fast-Neutron Reactors (Energoatomizdat, Moscow, 1985).
A. Walters and A. Reynolds, Reactors-Breeders on Fast Neutrons (Energoatomizdat, Moscow, 1989).
“Technical Means for Provision of RBN Safety,” in Mashinostroenie yadernoi tekhniki, Book 1, Ed. By O. E. Adamov (Mashinostroenie, Moscow, 2005).
R. M. Vosnesenski, N. V. Vyunnikov, V. P. Kornilov, et al., “Development of Passive Safety Devices for Emergency Protection of Fast Reactors,” in Proc. of Intern. Conf. 50 Years of Nuclear Power Engineering—Prospects for 50 Years (GNTs RF-FEI, Obninsk, 2004).
E. N. Serdun’, A. P. Sorokin, A. G. Portyanoi, et al., “Development and Studies of Passive Safety Devices on the Basis of Hydrocapillary Systems for Managing Severe Accidents,” Voprosy atomnoi nauki I tekhniki, Ser. Physics of Nuclear Reactors (RNTs Kurchatov Institute, Issue 3, 6–13 (2000).
P. A. Ushakov and A. P. Sorokin, “Role of Reynolds Criterion While Simulating Natural Convection in Liquid Metals,” Atomnaya Energiya 84(5), 388–394 (1998).
N. M. Matyukhin and A. P. Sorokin, “Approaches to Simulating Thermohydraulics of Fast Reactors with Liquid-Metal Cooling under Conditions of Emergency Cooling-down,” in Proc. of Interbranch Conf. “Teplofizika-2005”. Thermohydraulic Aspects of Safety of NPPs with Fast-Neutron Reactors, Obninsk, Russia, Nov. 17–18, 2005, p. 25.
Specialists’ Meeting on Evaluation of Decay Heat Removal by Natural Convection, International Atomic Energy IWGFR/88 (Oarai Eng. Center, PNC, Japan, 1993).
O. D. Kazachkovskii, A. V. Zhukov, A. P. Sorokin, and N. M. Matyukhin, “Temperature Fields in Fuel Assemblies of Fast Reactors with Form Distortion,” Atomnaya Energiya 85(2), 89–97 (1998).
I. N. Kravchenko, Yu. E. Bagdasarov, and Yu. I. Likhachev, “Strength Calculations of Fuel Rods and Hexahedral Fuel Assembly Shell with an Account of Distortion of Fuel-Rod Bundle and Shell in the Course of Their Irradiation in the Fast Reactor Core,” Preprint No. FEI-1840 (GNTs RF-FEI, Obninsk, 1987).
“LMFBR Core and Heat Exchanger Thermohydraulic Design: Former USSR and Present Russia Approaches,” IAEA-TECDOC-1060 (Vienna, IAEA, 1999).
A. P. Sorokin, A. D. Efanov, A. V. Zhukov, et al., “Thermohydraulic Studies of Increasing on Nuclear Fuel Burnup in Fast-Neutron Reactors,” Teploenergetika, No. 3, 9–16 (2007), [Thermal Engineering, No. 3 (2007)].
A. V. Zhukov, P. L. Kirillov, N. M. Matyukhin, et al., Thermohudraulic Design of Fuel Assemblies of Fast reactors with Liquid-Metal Cooling (Energoatomizdat, Moscow, 1985).
Yu. A. Kuzina, A. P. Sorokin, and A. V. Zhukov, “Numerical Simulation of Fuel Assembly Thermohydraulics in Reactors with Blockages,” Atomnaya Energiya 87(5), 342–356 (1999).
K. Miyaguchi and J. Takahashi, “Thermal Hydraulic Experiments and Simulated LMFBR Subassemblies under Normal and Non-nominal Operating Conditions,” IWGFR/29, 58–75 (1979).
H. Nukamura, K. Miyaguchi, and J. Takahashi, “Hydraulic Simulation of Local Blockages in LMFBR Fuel Subassemblies,” Nuclear Engineering and Design, 60(1–3), 323–333 (1980).
B. W. Spencer, et al., “Hydraulic Influences of Top-Generated Blockages in an LMFBR Subassembly,” Transactions of ANS, 34, 521–522 (1980).
W. T. Sha, “Effect of Partial Flow Blockages in an LMFBR Subasemblies,” Transactions of ANS, 15(1), 353–354 (1972).
M. Arai and N. Hirata, “Analysis of the Central Blockage Wake in an LMFBR Subassembly,” Nuclear Engineering and Design, 45(1), 127–132 (1978).
N. Hanus, et al., “Maximum Sodium Temperature Correlations for Six-Channel FBR Subassembly Blockage,” Transactions of ANS, 30, 417–418 (1978).
J. F. Dearing, “Calculated and Experimental Temperature Distribution behind Six-Channel Blockage,” Transactions of ANS, 27, 566–567 (1977).
D. Smidt and K. Schleisiek, “Fast Breeder Safety against Propagation of Local Failures,” Nuclear Engineering and Design, 40(3), 393–402 (1977).
P. A. Ushakov, Yu. S. Yur’ev, and A. P. Kolmakov, “Velocity, Pressure, and Temperature Fields in a Fuel-Rod Subassembly of Fast Reactors under Free-Flow Area Blockage,” in Teploobmen-V (Collection of papers), Ed. by A. G. Blokh (ITMO, Minsk, 1980), 8, pp. 173–180.
A. V. Zhukov, N. M. Matyukhin, and K. S. Rymkevich, “Effect of Free-Flow Area Blockage of a Fuel-Rod Assembly of a Fast Reactor on the Coolant Flow Distribution,” Preprint FEI-1479, GNTs RF-FEI, Obninsk, 1983.
Y. Kikuchi, “Local Sodium Boiling behind Local Flow Blockage in Simulated LMFBR Fuel Subassemblies,” Nuclear Science and Technology, 14(11), 774–790 (1977).
F. Huber and W. Peppler, “Summary and Application of Out-of-Pile Investigations of Local Coolant Disturbances in LMFBR Subassembly Geometry under Single-Phase and Boiling Conditions,” KFK-3927 (Kernforschungszentrum, Karlsruhe, 1985).
M. Arai and N. Hirata, “Numerical Calculation for Two-Phase Flow Analysis in Pin Bundles,” Nuclear Engineering and Design, 82(2–3), 157–169 (1984).
A. D. Efanov, A. P. Sorokin, E. F. Ivanov, et al., “An Investigation of the Heat Transfer and Stability of Liquid-Metal Coolant Boiling in a Natural Circulation Circuit,” Teploenergetika, No. 3, 20–26 (2003) [Thermal Engineering, 50 (3), 194–200 (2000)].
A. D. Efanov, A. P. Sorokin, E. F. Ivanov, et al., “Heat Transfer under Liquid-Metal Boiling in a System of Parallel Channels under Natural Circulation Regime,” Teploenergetika, No. 3, 43–51 (2007) [Thermal Engineering, 57 (3), (2007)]
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Original Russian Text ¢ A.P. Sorokin, 2007, published in Teploenergetika.
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Sorokin, A.P. Thermohydraulic studies of safety of NPPs with fast reactors. Therm. Eng. 54, 962–970 (2007). https://doi.org/10.1134/S004060150712004X
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DOI: https://doi.org/10.1134/S004060150712004X