Fast Reactors and Accelerator Driven Systems Knowledge Base

Conference Article: Issues of lead coolant technology

Yu.I. Orlov, P.N. Martynov, V.A. Gulevsky

Abstract

Starting from 1989 with the BREST-OD-300 reactor design development, some experimental studies related to lead coolant have been performed to provide feasibility of using liquid lead as a coolant in the closed circuit. Further comprehensive analytical and experimental studies are required to develop lead coolant technology for the BREST-OD-300 reactor design. General work program for justification of lead coolant technology are planned aiming at not only getting the information on the components required for the technology realization and their design features but also revealing the possibility of use of data obtained in the course of lead-bismuth circuit operation for the lead circuits. The main results performed so far for justification of BREST-OD-300 reactor coolant technology are presented in this paper. The results confirmed the possibility of using the experience gained on lead-bismuth coolant justification on the stage of the BREST-OD-300 reactor design development. In addition, the results provided directions for further justification of lead coolant technology based on experience gained on lead-bismuth coolant.

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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:102-105