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Conference Article: Fuel element for the gas-cooled fast breeder reactor BGR-300

Kolganov, V.D.; Kruglov, A.L.; Ulasevich, V.K.; Knyazev, V.A.; Tikhovov, N.I.; Ponomarev-Stepnoy, N.N.; Ashihmin, V.P.; Vorobjev, M.A

Abstract

The paper reviews general requirements and the conceptual approach to the development of fuel elements for a gas-cooled fast breeder reactor BGR-300 with helium coolant. The design of the sealed fuel rod is described and its technical characteristics are presented. The problems of fuel element experimental de-bugging are considered

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key words: Gas Cooled Reactor, Nuclear Technology
Reference:
Specialists' meeting on gas-cooled reactor fuel development and spent fuel treatment Moscow (Russian Federation) 18-21 Oct 1983
International Atomic Energy Agency, International Working Group on Gas-Cooled Reactors, Vienna (Austria); State Committee on the Utilisation of Atomic Energy of the USSR, Moscow (Russian Federation)
IWGGCR--8, pp:40-50