Published January 1987 | Version v1
Report Metadata-only

The integrity of CAGR moderator bricks

Creators

  • 1. UKAEA Risley Nuclear Power Development establishment

Description

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. (author)

Additional details

Publishing Information

Imprint Title
Summary report of the IAEA specialists' meeting on graphite component structural design
Imprint Pagination
254 p.
Journal Page Range
p. 20-28.
Report number
JAERI-M--86-192

Conference

Title
IAEA specialists' meeting on graphite component structural design.
Dates
8-11 Sep 1986.
Place
Tokai, Ibaraki (Japan).

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
18083186
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BRICKS; CRACKS; CREEP; GRAPHITE; HTGR TYPE REACTORS; LIFETIME; MECHANICAL TESTS; MODERATORS; OXIDATION; PHYSICAL RADIATION EFFECTS; SHRINKAGE; STRESSES
Descriptors DEC
BUILDING MATERIALS; CARBON; CHEMICAL REACTIONS; ELEMENTS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; MATERIALS; MATERIALS TESTING; MECHANICAL PROPERTIES; NONMETALS; RADIATION EFFECTS; REACTORS; TESTING

Optional Information

Secondary number(s)
IWGGCR--11.