Microhardness as a measure of embrittlement of pressure vessel steels
Description
The exposure of reactor pressure vessel steels to fast neutrons is known to result in reduced ductility and increased possibility of brittle failure. Initial research at the University of Virginia and previous measurements indicate that the microhardness test can be used as a supplemental nondestructive measurement of embrittlement. Increases in microhardness with irradiation correlate with shifts in the ductile to brittle transition temperature. It appears that the microhardness test can provide a direct measurement of the actual transition temperature, irradiation induced shifts in transition temperature and in uppershelf fracture energy. Thus, the microhardness test may provide a valid method for supplying the material property information required for safety analyses to prevent the premature shutdown of some operating nuclear power plants
Additional details
Publishing Information
- Imprint Title
- Transactions of the 1982 Eastern Regional American Nuclear Society student conference
- Journal Page Range
- p. 1, Paper 61.
- Report number
- DOE/ER/10275--1C
Conference
- Title
- American Nuclear Society regional student conference.
- Dates
- 16-17 Apr 1982.
- Place
- Atlanta, GA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16078117
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; EMBRITTLEMENT; MICROHARDNESS; PHYSICAL RADIATION EFFECTS; PRESSURE VESSELS; PWR TYPE REACTORS; REACTOR MATERIALS; STEELS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CONTAINERS; ENRICHED URANIUM REACTORS; HARDNESS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MECHANICAL PROPERTIES; POWER REACTORS; RADIATION EFFECTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS