HTGR Knowledge Base

Conference Article: Reactor tests of spherical fuel elements and HTGR microfuel elements and study of their state after irradiation

Gurin, V.A.; Degaltsev, Yu.G.; Ponomarev-Stepnoy, N.N.; Tikhonov, N.I.; Utkin, Yu.M.; Khrulev, A.A.; Chernikov, A.S.; Shtrombakh, Ya.I

Abstract

The ampoule and loop canal designs for irradiation of HTGR fuel elements and methods of investigation of their radiation stability are described. The results are presented on the measurement of fission product yield from fuel elements during irradiation. Irradiation main parameters are in agreement with HTGR operating conditions. The results of metallographic investigations of the micro fuel elements irradiated are given. The processes taking place in fuel elements and microfuel elements during irradiation are discussed

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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:226-243