Published October 2016
| Version v1
Miscellaneous
Influence of hydrogen gas on PWSCC mechanism of 690 alloy
- 1. Institute of Nuclear Safety System, Inc., Mihama, Fukui (Japan)
Description
no abstract available
Additional details
Publishing Information
- Imprint Title
- Proceedings of the 63rd Japan conference on materials and environments
- Imprint Pagination
- [368 p.]
- Journal Page Range
- p. 261-264
Conference
- Title
- 63. Japan conference on materials and environments
- Dates
- 17-19 Oct 2016
- Place
- Osaka (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 48020474
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- No Abstract, Conference, Non-conventional Literature
- Descriptors DEI
- ARGON; CRACKS; CREEP; DEFORMATION; DISLOCATIONS; GASEOUS DIFFUSION; GRAIN BOUNDARIES; HYDROGEN; INCONEL 600; INCONEL 690; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; STRESS CORROSION; STRESSES; TEMPERATURE RANGE 0400-1000 K
- Descriptors DEC
- ALLOY-NI59CR30FE9; ALLOY-NI76CR15FE8; ALLOYS; ALUMINIUM ADDITIONS; ALUMINIUM ALLOYS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; COOLING SYSTEMS; CORROSION; CORROSION RESISTANT ALLOYS; CRYSTAL DEFECTS; CRYSTAL STRUCTURE; DIFFUSION; ELEMENTS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; FLUIDS; GASES; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; INCONEL ALLOYS; IRON ALLOYS; LINE DEFECTS; MATERIALS; MECHANICAL PROPERTIES; MICROSTRUCTURE; NICKEL ALLOYS; NICKEL BASE ALLOYS; NIMONIC; NONMETALS; POWER REACTORS; RARE GASES; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; TEMPERATURE RANGE; THERMAL REACTORS; TITANIUM ADDITIONS; TITANIUM ALLOYS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS