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.
view the full text of this article (8 pages, format: PDF, size= 381kB)
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
- International Atomic Energy Agency, Vienna (Austria)
