Fast Reactors and Accelerator Driven Systems Knowledge Base

Conference Article: Post-irradiation examination of mixed (Pu, U)C fuels irradiated in the fast breeder reactor

Baldev, R.;Kasiviswanathan, K.V.;Venugopal, V. (Metallurgy and Materials Group, Indira Gandhi Centre for Atomic Research, Kalpakkam (India)) (and others)

Abstract

The Fast Breeder Test Reactor (FBTR) at Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam, India, using mixed (Pu,U)C fuel has completed eleven years of operation. One fuel subassembly which has seen more than 25,000 MWd/t burn-up has been discharged from this reactor taken up for post-irradiation examination. The PIE carried out on this fuel subassembly has established that the fuel has performed satisfactorily and it is capable of being taken to higher levels of burn-up and linear heat ratings. The facilities available for PIE of advanced fuels and the PIE work carried out are discussed in detail in this paper.

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key words: Fast Neutron Spectrum Systems, Nuclear Technology
Reference:
Influence of high dose irradiation on core structural and fuel materials in advanced reactors. Technical committee meeting, Obninsk (Russian Federation), 16-19 Jun 1997
International Atomic Energy Agency, Vienna (Austria)
IAEA-TECDOC--1039, pp:57-68