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Georgy Toshinsky; Vladimir Petrochenko (2012)
Publisher: MDPI AG
Journal: Sustainability
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”.
  • The results below are discovered through our pilot algorithms. Let us know how we are doing!

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    • 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.
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