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Title: Effects of irradiation temperature on embrittlement of nuclear pressure vessel steels

Conference ·
OSTI ID:7368458

The effects of neutron irradiation on the steel reactor vessel for the modular high-temperature gas-cooled reactor (MHTGR) are being investigated, primarily because the operating temperatures are low [121 to 288[degrees]C (250--550[degrees]F)] compared to those for commercial light-water reactors (LWRs) [[approximately]288[degrees]C (550[degrees]F)]. The need for design data on the reference temperature (RT[sub NDT]) shift necessitated the irradiation at different temperatures of A 533 grade B class 1 plates, A 508 class 3 forging, and welds used for the vessel shell, vessel closure head, and vessel flange. This paper presents regular- and mini-tensile, Automated Ball Indentation (ABI), and Charpy V-notch (CVN) impact test results from five irradiation capsules of this program.

Research Organization:
Oak Ridge National Lab., TN (United States)
Sponsoring Organization:
USDOE; USDOE, Washington, DC (United States)
DOE Contract Number:
AC05-84OR21400
OSTI ID:
7368458
Report Number(s):
CONF-920673-18; ON: DE93015428
Resource Relation:
Conference: 16. annual symposium of American Society of Testing and Materials (ASTM) on effects of radiation on materials, Denver, CO (United States), 21-25 Jun 1992
Country of Publication:
United States
Language:
English