Published 1985
| Version v1
Book
Irradiation embrittlement behavior of some Japanese reactor vessel steels
Creators
- 1. Takasago Technical Inst., Mitsubishi Heavy Industries, Ltd., Takasago City, Hyogo Pref.
Description
Neutron embrittlement behavior of Japanese pressure vessel steels was analyzed. Cu contents of Japanese steels are less than the reported data in another country, and generally plate materials controls embrittlement behavior. The NRC R.G.1.99 were conservative. New predictive equations were proposed by statistical analysis
Additional details
Publishing Information
- Publisher
- American Society of Metals.
- Imprint Place
- Metals Park, OH (USA)
- Imprint Title
- Proceedings of the international conference on nuclear power plant aging, availability factor and reliability analysis
- Journal Page Range
- p. 169-172.
Conference
- Title
- International conference on nuclear power plant aging, availability factor and reliability analysis.
- Dates
- 7-12 Jul 1985.
- Place
- San Diego, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17073326
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COPPER; DAMAGING NEUTRON FLUENCE; IRRADIATION; JAPAN; PHYSICAL RADIATION EFFECTS; POWER REACTORS; PREDICTION EQUATIONS; PRESSURE VESSELS; REACTOR MATERIALS; STATISTICS; STEELS; US NRC
- Descriptors DEC
- ALLOYS; ASIA; CARBON ADDITIONS; CONTAINERS; DEVELOPED COUNTRIES; ELEMENTS; EQUATIONS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MATHEMATICS; METALS; NATIONAL ORGANIZATIONS; NEUTRON FLUENCE; RADIATION EFFECTS; REACTORS; TRANSITION ELEMENTS; US ORGANIZATIONS