Fracture toughness characterization of Japanese reactor pressure vessel steels: Joint EPRI-CRIEPI RPV embrittlement studies. Final report
- Materials Engineering Associates, Inc., Lanham, MD (United States)
- ATI Consulting, San Ramon, CA (United States)
The properties of five Japanese reactor pressure vessel steels have been characterized. These steels represent three A533-B C1 1 plates and two A 508 C1 3 forgings produced over a 20-year period, from 1969 to 1989. The fracture toughness was characterized by means of the J-R curve. Also investigated were the Charpy V-Notch and tensile properties as well as chemical composition and metallography. The five specimens were found to be essentially identical in the areas investigated. The test results for the five Japanese steels provide the unirradiated baseline needed for evaluating the effects of radiation embrittlement. Several of these Japanese materials are being irradiated in power and test reactors as part of the EPRI/CRIEPI Joint Research Project.
- Research Organization:
- Electric Power Research Inst., Palo Alto, CA (United States); Materials Engineering Associates, Inc., Lanham, MD (United States); ATI Consulting, San Ramon, CA (United States)
- Sponsoring Organization:
- Electric Power Research Inst., Palo Alto, CA (United States)
- OSTI ID:
- 10171115
- Report Number(s):
- EPRI-TR-102409; CRIEPI-T-989203; ON: UN93017392; TRN: 93:020987
- Resource Relation:
- Other Information: PBD: May 1993
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
36 MATERIALS SCIENCE
PRESSURE VESSELS
MECHANICAL PROPERTIES
REACTOR VESSELS
STEEL-ASTM-A533-B
STEEL-ASTM-A508
FRACTURE PROPERTIES
EMBRITTLEMENT
TENSILE PROPERTIES
CHARPY TEST
TRANSITION TEMPERATURE
JAPAN
RADIATION EFFECTS
CHEMICAL COMPOSITION
METALLOGRAPHY
MICROSTRUCTURE
CRACKS
CRACK PROPAGATION
EXPERIMENTAL DATA
220200
360103
360106
COMPONENTS AND ACCESSORIES