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Title: Fracture toughness characterization of Japanese reactor pressure vessel steels: Joint EPRI-CRIEPI RPV embrittlement studies. Final report

Technical Report ·
OSTI ID:10171115
; ;  [1];  [2]
  1. Materials Engineering Associates, Inc., Lanham, MD (United States)
  2. 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