Published 1998
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Reactor pressure vessel steels
Description
Research and development activities related to reactor pressure vessel steels during 1997 are reported. The objectives of activities of the Belgian Nuclear Research Centre SCK/CEN in this domain are: (1) to develop enhanced surveillance concepts by applying micromechanics and fracture-toughness tests to small specimens, and by performing damage modelling and microstructure characterization; (2) to demonstrate a methodology on a broad database; (3) to achieve regulatory acceptance and industrial use
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30057832.pdf
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Additional details
Publishing Information
- Imprint Title
- 1997 Scientific Report
- Imprint Pagination
- 130 p.
- Journal Page Range
- p. 48-54
- Report number
- INIS-BE--0002
INIS
- Country of Publication
- Belgium
- Country of Input or Organization
- Belgium
- INIS RN
- 30057832
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Progress Report
- Descriptors DEI
- ALUMINIUM; BR-2 REACTOR; BR-3 REACTOR; CHARPY TEST; FRACTURE MECHANICS; FRACTURE PROPERTIES; INSPECTION; OBRIGHEIM REACTOR; PRESSURE VESSELS; PROGRESS REPORT; REACTOR VESSELS; WELDED JOINTS
- Descriptors DEC
- CONTAINERS; DESTRUCTIVE TESTING; DOCUMENT TYPES; ELEMENTS; ENRICHED URANIUM REACTORS; IMPACT TESTS; IRRADIATION REACTORS; JOINTS; MATERIALS TESTING; MATERIALS TESTING REACTORS; MECHANICAL PROPERTIES; MECHANICAL TESTS; MECHANICS; METALS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; TANK TYPE REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- The abstract is a contribution to the 1997 Scientific Report of the Belgian Nuclear Research Centre SCK-CEN