Evaluation for material inspection of graphite inspection standard in High Temperature Engineering Test Reactor
Creators
- 1. Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment
Description
The graphite inspection standard for the High Temperature Engineering Test Reactor (HTTR) consists of material, nondestructive, dimensional and visual inspections. The inspection method and judgement criteria in the material inspection are nor detailed in some items, although some explanations are provided for the items especially necessary to be considered in the inspection. Therefore, inspection method and judgement criteria in the material inspection which contains material grade, impurity and mechanical strength inspections, are fully evaluated on the basis of the feature of these materials. Material inspection method and judgement criteria for HTTR graphite and carbon are evaluated in consideration of the research data and manufacturing experiences. As a result, inspection method and judgement criteria can be established, which are to be applied to the graphite and carbon internal acceptance tests of HTTR. (author)
Availability note (English)
MF available from INIS under the Report Number.Files
24054733.pdf
Files
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Additional details
Publishing Information
- Imprint Pagination
- 33 p.
- Report number
- JAERI-M--93-002
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 24054733
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CARBON; GRAPHITE; HTTR REACTOR; IMPURITIES; INSPECTION; MECHANICAL TESTS; NONDESTRUCTIVE TESTING; STABILITY; THERMAL EXPANSION
- Descriptors DEC
- ELEMENTS; ENRICHED URANIUM REACTORS; EXPANSION; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; MATERIALS TESTING; NONMETALS; REACTORS; RESEARCH AND TEST REACTORS; TESTING