Published May 2009
| Version v1
Miscellaneous
Systematization of assessment techniques of stress corrosion cracking for in-vessel components and piping in BWR
- 1. Japan Atomic Energy Agency, Tokai, Ibaraki (Japan)
Description
no abstract available
Additional details
Publishing Information
- Imprint Title
- Proceedings of JSCE materials and environments 2009
- Imprint Pagination
- 428 p.
- Journal Page Range
- p. 29-32
Conference
- Title
- JSCE materials and environments 2009
- Dates
- 22-24 May 2009
- Place
- Tokyo (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 42051500
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- No Abstract, Conference, Non-conventional Literature
- Descriptors DEI
- BWR TYPE REACTORS; COMPARATIVE EVALUATIONS; CRACK PROPAGATION; CRACKS; INSPECTION; NUCLEAR INDUSTRY; PIPES; REACTOR MATERIALS; STAINLESS STEEL-304; STRESS CORROSION; TEMPERATURE RANGE 0400-1000 K; WATER CHEMISTRY
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHEMICAL REACTIONS; CHEMISTRY; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; CORROSION; CORROSION RESISTANT ALLOYS; ENRICHED URANIUM REACTORS; EVALUATION; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; INDUSTRY; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; NICKEL ALLOYS; POWER REACTORS; REACTORS; STAINLESS STEELS; STEEL-CR19NI10; STEELS; TEMPERATURE RANGE; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; TUBES; WATER COOLED REACTORS; WATER MODERATED REACTORS