Fast Reactors and Accelerator Driven Systems Knowledge Base

Conference Article: Use of Russian technology of ship reactors with lead-bismuth coolant in nuclear power

Zrodnikov, A.V.; Chitaykin, V.I.; Gromov, B.F.; Grigoryv, O.G.; Dedoul, A.V.; Toshinsky, G.I. (Institute of Physics and Power Engineering, Obninsk, Kaluga Region (Russian Federation)); Dragunov, Yu.G.; Stepanov, V.S. (EDO 'Gidropress', Podoolsk, Moscow (Russian Federation))

Abstract

The experience of using lead-bismuth coolant in Russian nuclear submarine reactors has been presented. The fundamental statements of the concept of using the reactors cooled by lead-bismuth alloy in nuclear power have been substantiated. The key results of developments for using lead-bismuth coolant in nuclear power have been presented.

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key words: bismuth; coolants; heat transfer; lead alloys; lead; liquid metals; mass transfer; ship propulsion reactors; submarines
Reference:
Advisory group meeting on small power and heat generation systems on the basis of propulsion and innovative reactor technologies. Obninsk (Russian Federation) 20-24 Jul 1998
International Atomic Energy Agency, Vienna (Austria)
IAEA-TECDOC--1172, pp:129-157