Fast Reactors and Accelerator Driven Systems Knowledge Base

Conference Article: Evolution of the technical concepts of fast reactors: The concept of BREST

V.V. Orlov

Abstract

A new reactor concept BREST, which will adequately meet the variety of cost-efficiencies and safety requirements set for power industry demand within contemporary understandings, has been developed based on the lessons learned from a 50-year experience in the fast reactor development in Russia. The BREST reactor concept adopts most features of the IFR concept. However, several advances in consistent implementation of natural safety principle and in increase of unit power without sacrifice due to its reduction have been achieved in the BREST reactor design. Applications of the high dense and heat-conductive mono-nitride fuel, and the lead-bismuth coolant having high degree of natural circulation are incorporated to facilitate the long-lived high-level radwaste treatment and the natural safety principles in the BREST reactor design. The 40-year experience gained in the lead-bismuth cooled submarine development and the results obtained from core physics experiments and lead coolant experimental works allowed to begin detailed design of a demonstration power unit consisting of BREST-300 reactor and on-site fuel cycle facilities. The construction of the BREST-300 power unit is scheduled for its completion in the first decade of the 21st century. A feasibility study for two BREST-1200 power units demonstrated its superior economics to LWRs of the same power output. Several calculational and experimental works, and design efforts for clarifying the applicability of developed lead-bismuth coolant technology to the lead coolant are under way. An international cooperation on those efforts would substantially contribute to the BREST reactor development.

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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:30-35