Published September 2013 | Version v1
Miscellaneous Metadata-only

Role of cavity formation in SCC of cold worked alloy 690 in high-temperature water

Creators

  • 1. Institute of Nuclear Safety System, Inc., Mihama, Fukui (Japan)

Description

no abstract available

Part of:
Proceedings of the 60th Japan conference on materials and environments

Additional details

Publishing Information

Imprint Title
Proceedings of the 60th Japan conference on materials and environments
Imprint Pagination
362 p.
Journal Page Range
p. 111-114

Conference

Title
60. Japan conference on materials and environments
Dates
24-26 Sep 2013
Place
Fukushima (Japan)

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
45077921
Subject category
S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
No Abstract, Conference, Non-conventional Literature
Descriptors DEI
CAVITIES; COLD WORKING; CRACK PROPAGATION; CRACKS; CREEP; DEPTH; HEAT TREATMENTS; INCONEL 690; INTERGRANULAR CORROSION; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR MATERIALS; STRESS CORROSION; TEMPERATURE DEPENDENCE; TEMPERATURE RANGE 0400-1000 K
Descriptors DEC
ALLOY-NI59CR30FE9; ALLOYS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; COOLING SYSTEMS; CORROSION; CORROSION RESISTANT ALLOYS; DIMENSIONS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; FABRICATION; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; INCONEL ALLOYS; IRON ALLOYS; MATERIALS; MATERIALS WORKING; MECHANICAL PROPERTIES; NICKEL ALLOYS; NICKEL BASE ALLOYS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; TEMPERATURE RANGE; THERMAL REACTORS; TITANIUM ADDITIONS; TITANIUM ALLOYS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information