HTGR Knowledge Base

Conference Article: The integrity of CAGR moderator bricks

Prince, N. (UKAEA Risley Nuclear Power Development establishment); Brocklehurst, J.E

Abstract

The procedures for assessing the integrity of moderator bricks in Advanced Gas Cooled Reactors is described together with experiments proposed to improve the graphite input data and verify the condition of bricks at the end of life.

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key words: bricks; cracks; creep; graphite; htgr type reactors; lifetime; mechanical tests; moderators; oxidation; physical radiation effects; shrinkage; stresses; building materials; carbon; chemical reactions; gas cooled reactors; graphite moderated reactors; materials testing; mechanical properties; radiation effects
Reference:
Specialists' meeting on graphite component structural design, JAERI Tokai (Japan), September 8-11, 1986
International Atomic Energy Agency, Vienna (Austria). International Working Group on Gas-Cooled Reactors
IWGGCR--11, pp:20-28