Fast Reactors and Accelerator Driven Systems Knowledge Base

Conference Article: Nuclear power strategy: Requirements for technology

V.V. Orlov, V.I. Rachkov

Abstract

Principle design features of BREST-300 (300 MWe) and BREST-1200 (1200 MWe) lead-cooled fast reactors are presented in this paper. Several experimental works have been performed or under way in order to justify lead-cooled reactor design concepts. BREST reactor designs of different outputs have been developed using the same principles. In conjunction with the increased output and the implement of inherent safety concept, a number of new solutions, which may be applied to the BREST-300 reactor design too, have been considered in the BREST-1200 reactor design. The new design features adopted in the BREST-1200 reactor design include: pool?type reactor design not requiring metal vessel, hence, not limiting reactor power; new handling system allowing to reduce central hall and building dimensions as a whole; emergency cooling system using field pipes, immersed directly in lead, which may be used to cool down reactor under normal conditions; by?pass line incorporated in coolant loop allowing to refuse the actively actuating valve initiated in pumps shut down.

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key words: Fast Neutron Spectrum Systems, Nuclear Technology
Reference:
Advisory Group Meeting on “Design and Performance of Reactor and Sub-critical Blanket Systems with Lead and Lead-Bismuth as Coolant and/or Target Material” , Moscow, Russian Federation, 23-27 October 2000
International Atomic Energy Agency, Vienna (Austria)
IAEA-TECDOC--1348, pp:13-19