材料科学
冶金
应力腐蚀开裂
腐蚀
合金
冷却液
焊接
压水堆
开裂
应变率
压力(语言学)
复合材料
核工程
语言学
哲学
物理
核物理学
工程类
作者
G.F Li,E.A. Charles,J. Congleton
标识
DOI:10.1016/s0010-938x(00)00182-7
摘要
Abstract The susceptibility to stress corrosion cracking (SCC) of a low alloy to stainless steel transition weld, A508-309L/308L, in simulated pressurised water reactor (PWR) primary water, contaminated with low levels of sulphate, at 292°C was assessed via slow strain rate tests under controlled potentials and static load tests at free corrosion potentials. The minimum potential for SCC, Ec, and crack growth rate were used to evaluate the susceptibility of as-welded and post-weld heat treated material. U-bend specimens tested at open circuit potential showed no SCC. The results indicate that if exposed, the transition weld should be immune to SCC in PWR primary side coolant water.
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