STRESS CORROSION CRACKING OF NEUTRON IRRADIATED AUSTENITIC STAINLESS STEEL IN SCW
The Irradiated Materials Testing Laboratory was built to provide the capability to conduct corrosion and stress corrosion cracking tests on neutron irradiated samples in a supercritical water environment. The laboratory has the capability to test samples in constant extension rate tensile (CERT) or crack growth rate (CGR) modes and to conduct post-test fracture analysis vis scanning electron microscopy. Pin-loaded tensile samples irradiated at 407, 427℃ or 520℃ in FFTF to doses up to 44 dpa were tested in CERT mode in deaerated SCW at temperatures similar to the irradiation temperatures. All samples tested in 400℃ SCW exhibited intergranular stress corrosion cracking, low strain to failure and low reduction in area. The sample tested at 520℃ also exhibited severe IGSCC but failed in the grip. From existing data on the tensile behavior of this alloy tested in room temperature air, the SCW environment appears to have resulted in significant embrittlement.
S.Teysseyre G.S.Was
University of Michigan
国际会议
上海
英文
320
2007-03-12（万方平台首次上网日期，不代表论文的发表时间）