HTGR Knowledge Base

Conference Article: A comparison of predicted and measured graphite moderator behaviour during 16 years' operation of the Windscale advanced gas-cooled reactor

Prince, N. (Thermal Reactor Development Directorate, UKAEA, Northern Div., Risley, Warrington, UK)

Abstract

The Windscale AGR has operated since January 1963 at a cumulative load factor of nearly 70% during which time the peak irradiation damage dose has built up to more than 5x10 n/cm2 (equivalent DIDO nickel), well beyond its original design life. This paper recounts the findings of monitoring measurements on the moderator at high exposure levels with regard to radiolytic oxidation and various aspects of dimensional change behaviour. It is shown that the measured dimensional changes are in good agreement with predictions based on small specimens irradiated in MTR's, thus confirming the absence of any size effect and adding confidence to predictive methods. However, recent measurements of channel straightness show that the observed distortions are only about 10% of the maximum predictions, perhaps due to localised creep at the brick ends creating flats which impart some stability to the columns of moderator bricks. The magnitude of radiolytic oxidation determined by trepanning specimens from the core in 1976 was found to be only about 5%, whereas it was thought possible that peak weight losses would conceivably be as high as 11% due to the depleted concentration of methane inhibitor reaching the brick interior by diffusion processes. It has subsequently been shown by calculation that this result is consistent with the existence of radial pressure drops across the moderator brick walls giving greater penetration of methane inhibitor.

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key words: graphite; moderators; monitoring; physical radiation effects; shrinkage; testing; wagr reactor; agr type reactors; carbon dioxide cooled reactors; carbon; elements; enriched uranium reactors; gas cooled reactors; graphite moderated reactors; power reactors; thermal reactors
Reference:
Specialists meeting on mechanical behaviour of graphite for HTRs, Gif-sur-Yvette, France, 11-13 June 1979.
International Atomic Energy Agency, Vienna (Austria). International Working Group on High-Temperature Reactors.
IWGHTR--3, pp:21-35