Published 1987
| Version v1
Book
Hydrogen buildup in irradiated Type-304 stainless steel
Description
Type-304 stainless steel (SS), irradiated to a range of fast (E > 1 MeV) neutron fluences (1.90 x 10/sup 18/ to 9 x 10/sup 21/) in several different boiling water reactors, was found to contain ≥3 times as much hydrogen as unirradiated material. Hydrogen buildup in irradiated Type-304 SS was independent of fluence and flux in the range of fluences and fluxes investigated. This study was conducted as part of an investigation of irradiation-assisted stress corrosion cracking (IASCC). The accumulation of hydrogen in irradiated Type-304 SS may exacerbate the irradiation-induced loss of ductility, thereby increasing susceptibility to IASCC, or it may contribute to IASCC by other means
Additional details
Publishing Information
- Publisher
- ASTM.
- Imprint Place
- Philadelphia, PA (USA)
- ISBN
- 0-8031-0963-6
- Imprint Title
- Influence of radiation on material properties: ASTM 13th international symposium (Part II)
- Journal Page Range
- p. 239-244.
Conference
- Title
- 13. international symposium on the effects of radiation on materials.
- Dates
- 23-25 Jun 1986.
- Place
- Seattle, WA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19098973
- Subject category
- S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE; S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Quality check status
- Yes
- Descriptors DEI
- BWR TYPE REACTORS; DAMAGING NEUTRON FLUENCE; DUCTILITY; EMBRITTLEMENT; HYDROGEN; HYDROGEN ADDITIONS; IRRADIATION; PHYSICAL RADIATION EFFECTS; REACTOR MATERIALS; REACTOR SAFETY; STEEL-CR19NI10; STRESS CORROSION;
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; CORROSION; CORROSION RESISTANT ALLOYS; ELEMENTS; ENRICHED URANIUM REACTORS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MECHANICAL PROPERTIES; NEUTRON FLUENCE; NICKEL ALLOYS; NONMETALS; POWER REACTORS; RADIATION EFFECTS; REACTORS; SAFETY; STAINLESS STEELS; STEELS; TENSILE PROPERTIES; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS;