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Conference Article: SVBR-75: a reactor module for renewal of WWER-440 decommissioning reactors - safety and economic aspects

Stepanov, V.S.; Kulikov, M.L.; Ilyin, O.G.; Klimov, N.N. (EDB 'Gidropress', Podol'sk (Russian Federation)); Chekunov, V.V.; Grigoriev, O.G.; Gromov, B.F.; Leonchyk, M.P.; Pashkin, Yu.G.; Pankratov, D.V.; Toshinsky, G.I.; Skorikov, D.E. (SSC RF IPPE, Obninsk (Russian Federation))

Abstract

IPPE has been developing jointly with EDB 'Gidropress' a reactor called SVBR-75 (in English spelling LBFR-75: Lead-Bismuth Fast Reactor), an innovative heavy metal reactor with transparent safety characteristics. The SVBR-75 Reactor Module is designed for the steam production instead of WWER-440 reactors to be decommissioned. At the renewal of the NPP unit the reactor vessel is remained at the same place, and steam generators are replaced by the new modules for SVBR-75. The main targets are: passively safe behaviour, no pressurisation of the reactor containment (building) under any accident conditions, reduction of plant capital costs and the construction schedule by means of the modular concept and the compact layout. The SVBR-75 design, described in general terms in this paper, is based upon the safety concept proposed by IPPE and on proven technology from both LMR and HMR for submarines.

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key words: Gas Cooled Reactor, Nuclear Technology
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Advisory group meeting on technology, design and safety aspects of non-electrical application of nuclear energy, 20-24 October 1997.
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Advisory group meeting on materials and equipment for the coupling interfaces of nuclear reactors with desalination and district heating plants, 21-23 April 1998.
International Atomic Energy Agency, Vienna (Austria)
IAEA-TECDOC--1056, pp:165-176