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(Irradiation embrittlement of reactor pressure vessels)

Technical Report ·
DOI:https://doi.org/10.2172/6565390· OSTI ID:6565390
The traveler served as a member of the two-man US Nuclear Regulatory Commission sponsored team who visited the Prometey Complex in Leningrad to assess the potential for expanded cooperative research concerning integrity of the primary pressure boundary in commercial light-water reactors. The emphasis was on irradiation embrittlement, structural analysis, and fracture mechanics research for reactor pressure vessels. At the irradiation seminar in Cologne, presentations were made by German, French, Finnish, Russian, and US delegations concerning many aspects of irradiation of pressure vessel steels. The traveler made presentations on mechanisms of irradiation embrittlement and on important aspects of the Heavy-Section Steel Irradiation Program results of irradiated fracture mechanics tests.
Research Organization:
Oak Ridge National Lab., TN (USA)
Sponsoring Organization:
NRC
DOE Contract Number:
AC05-84OR21400
OSTI ID:
6565390
Report Number(s):
ORNL/FTR-3753; ON: DE91000382
Country of Publication:
United States
Language:
English