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Toshinsky, Georgy; Petrochenko, Vladimir (2012)
Publisher: Molecular Diversity Preservation International
Journal: Sustainability
Languages: English
Types: Article
Subjects: TD194-195, Renewable energy sources, fast reactor, lead bismuth; fast reactor; reactor safety; SVBR-100; potential energy; nuclear fuel cycle; uranium oxide, SVBR-100, reactor safety, potential energy, TJ807-830, GE1-350, Environmental sciences, lead bismuth, Environmental effects of industries and plants, nuclear fuel cycle, uranium oxide
jel: jel:Q2, jel:Q3, jel:Q0, jel:Q, jel:Q5, jel:Q56, jel:O13
On the basis of the unique experience of operating reactors with heavy liquid metal coolant–eutectic lead-bismuth alloy in nuclear submarines, the concept of modular small fast reactors SVBR-100 for civilian nuclear power has been developed and validated. The features of this innovative technology are as follows: a monoblock (integral) design of the reactor with fast neutron spectrum, which can operate using different types of fuel in various fuel cycles including MOX fuel in a self-providing mode. The reactor is distinct in that it has a high level of self-protection and passive safety, it is factory manufactured and the assembled reactor can be transported by railway. Multipurpose application of the reactor is presumed, primarily, it can be used for regional power to produce electricity, heat and for water desalination. The Project is being realized within the framework of state-private partnership with joint venture OJSC “AKME-Engineering” established on a parity basis by the State Atomic Energy Corporation “Rosatom” and the Limited Liability Company “EuroSibEnergo”.
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    • International Atomic Energy Agency (IAEA). Guidance for the Evaluation of Innovative Nuclear Reactors and Fuel Cycles: Report of Phase 1A of INPRO; IAEA-TECDOC-1362; IAEA: Vienna, Austria, 2003.
    • Zrodnikov, A.V.; Toshinsky, G.I.; Stepanov, V.S.; Komlev, O.G.; Stepanov, V.S.; Klimov, N.N.; Generalov, V.N.; Kopytov, I.I.; Krushelnitsky, V.N. Innovative nuclear technology based on modular multi-purpose lead-bismuth cooled fast reactors. Prog. Nuclear Energy 2008, 50, 170-178.
    • Zrodnikov, A.V.; Toshinsky, G.I.; Dragunov, Y.G.; Stepanov, V.S.; Klimov, N.N.; Kopytov, I.I.; Krushelnitsky, V.N.; Yermakov, N.I.; Kornienko, A.G. Lead-Bismuth Reactor Technology Conversion: From Nuclear Submarine Reactors to Power Reactors and Ways to Increase the Investment Attractiveness of Nuclear Power Based on Fast-Neutron Reactors. In Proceedings of IAEA International Conference “Fifty Years of Nuclear Power-The Next Fifty Years”, Obninsk, Russia, 27 June-2 July 2004.
    • 4. Leypunsky, A.I. Fast Neutron Systems. In Selected Papers. Reminiscence; Naukova Dumka: Kiev, Ukraine, 1990; p. 62.
    • 5. Pankratov, D.V.; Yefimov, Y.I.; Toshinsky, G.I.; Ryabaya, L.D. Analysis of Polonium Hazard in Nuclear Power Installations with Lead-Bismuth Coolant. In Proceedings of International Congress on Advances in Nuclear Power Plants (ICAPP'05), Seoul, Korea, 15-19 May 2005.
    • 6. Wiggs, L.D.; Cox-De Vore, C.A.; Voelz, G.L. Mortality among a Cohort of Workers Monitored for Po-210 Exposure: 1944-1972 y.y. Epidemiology Section Occupational Medicine Group; Health Physics-Los Alamos National Laboratory: Los Alamos, NM, USA, 1991; Volume 61.
    • 7. ARMZ Uranium Holding Co. (AtomRedMetZoloto). The Analysis of Bismuth Mineral Resources in Russia, CIS and in the World; Report; ARMZ Uranium Holding Co. (AtomRedMetZoloto): Moscow, Russia, 2000.
    • 8. Masakazu, I. A Conceptual Design Study on Various Types of HLMC Fast Reactor Plant. In Proceedings of Lead-Bismuth Technology International Meeting, OEC/JNC/Japan, O-Arai, Japan, 12-14 December 2000.
    • 9. Gromov, B.F.; Grigoriev, O.G.; Dedoul, A.V.; Toshinsky, G.I.; Stepanov V.S.; Nikitin, L.B. The Analysis of Operation Experience of Reactor Installations Using Lead-Bismuth Coolant and Accidents Happened. In Proceeding of the Conference “Heavy Liquid Metal Coolants in Nuclear Technology” (HLMC-98), Obninsk, Russia, 5-9 October 1998; Volume 1, pp. 63-69.
    • 10. Gromov, B.F.; Orlov, Y.I.; Martynov, P.N.; Gulevsky, V.A. The Problems of Technology of the Heavy Liquid Metal Coolants. In Proceeding of the Conference “Heavy Liquid Metal Coolants in Nuclear Technology” (HLMC-98), Obninsk, Russia, 5-9 October 1998; Volume 1, pp. 87-100.
    • 11. Toshinsky, G.I.; Komlev, O.G.; Tormyshev, I.V.; Danilenko, K.Y. Effect of Potential Energy Stored in Reactor Facility Coolant on NPP Safety and Economic Parameters. In Proceedings of International Congress on Advances in Nuclear Power Plants (ICAPP 2011), Nice, France, 2-5 May 2011.
    • 12. Gat, U. The Ultimate Safe (U.S.) Reactor. In Proceedings of ICENES-4, Madrid, Spain, 1987; World Sci. Publ. Co.: Madrid, Spain, pp. 584-595.
    • 13. Novikov, V.M.; Slessarev, I.S.; Alekseyev, P.N.; Ignatyev, V.V.; Subbotin, S.A. Nuclear Reactors of Enhanced Safety. The Analysis of Conceptual Designs; Energoatomizdat Publishers: Moscow, Russia, 1993; p. 52.
    • 14. International Atomic Energy Agency (IAEA). Advanced Nuclear Plant Design Options to Cope with External Events; IAEA-TECDOC-1487; IAEA: Vienna, Austria, February 2006. Available online: http://www-pub.iaea.org/MTCD/publications/PDF/te_1487_web.pdf (accessed on 14 September 2012).
    • 15. Zrodnikov, A.V.; Toshinsky, G.I.; Dragunov, Y.G.; Stepanov, V.S.; Komlev, O.G.; Klimov, N.N.; Kopytov, I.I.; Krushelnitsky, V.N. Nuclear power development in market conditions with use of multi-purpose modular fast reactors SVBR-75/100. Nuclear Eng. Des. 2006, 236, 1490-1502.
    • 16. Toshinsky, G.I.; Komlev, O.G.; Stepanov V.S.; Novikova, N.N.; Tormyshev, I.V.; Klimov, N.N.; Dedoul, A.V. Principles of Providing Inherent Self-Protection and Passive Safety Characteristics of the SVBR-75/100 Type Modular Reactor Installation for Nuclear Power Plants of Different Capacity and Purpose. In Proceedings of International Conference Advanced Nuclear Fuel Cycles and Systems (GLOBAL'07), Boise, ID, USA, 9-13 September 2007.
    • 17. Novikova, N.N.; Komlev, O.G.; Toshinsky, G.I. Neutronic and Physical Characteristics of Reactor SVBR-75/100 with Different Types of Fuel. In Proceedings of ICAPP '06, Reno, NV, USA, 4-8 June 2006.
    • 18. Zrodnikov, A.V.; Toshinsky, G.I.; Komlev, O.G.; Melnikov, K.G.; Novikova, N.N. Fuel cycle for reactor SVBR-100. J. Mater. Sci. Eng. B 1, 2011, 1, 929-937.
    • 19. Chung, K.S.; Lee, J.S.; Song, K.S.; Song, K.C.; Yang, M.S. Research and Development Program of KAERI for DUPIC. In Proceedings of International Conference on Future Nuclear Systems: Emerging Fuel Cycles and Waste Disposal Options, GLOBAL'93, Seattle, WA, USA, 12-17 September 1993; American Nuclear Society: La Grange Park, IL, USA, 1993; Volume 2, p. 733.
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