HTGR Knowledge Base

Conference Article: Application of a method for assessing probability of graphite core brick failure

Judge, R.C.B. (AEA Technology, Harwell (United Kingdom))

Abstract

At the IAEA Specialist Meeting on the Status of Graphite Development for Gas Cooled Reactors, held in Japan 1991, the author presented a conceptual probabilistic approach to assessing graphite core brick integrity. This took account of variabilities in material properties and operational environment. The original concept has since been developed to the stage where it can be applied. This paper describes the implementation of the method to derive probabilities of failure for AGR graphite core bricks.

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key words: Gas Cooled Reactor, Nuclear Technology
Reference:
Specialists meeting on graphite moderator lifecycle behaviour. Bath (United Kingdom). 24-27 Sep 1995.
International Atomic Energy Agency, Vienna (Austria)
IAEA-TECDOC--901, pp:117-124