首页> 美国政府科技报告 >Reactor Primary Coolant System Pipe Rupture Study Method for Detection of Sensitization in Stainless Steel. Progress Report No. 42, October--December 1977
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Reactor Primary Coolant System Pipe Rupture Study Method for Detection of Sensitization in Stainless Steel. Progress Report No. 42, October--December 1977

机译:反应堆一次冷却系统管道破裂研究方法检测不锈钢敏化。 1977年10月至12月第42号进展报告

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摘要

A program is in progress to develop a quantitative method (EPR) for nondestructively measuring the degree of sensitization in Type-304 and -304L stainless steels. The technique has been extended to characterize weld heat-affected zones and to correlate degree of sensitization with intergranular stress-corrosion cracking resistance. Current studies are directed toward establishing procedures for, and qualifying, a technique to obtain EPR measurements in-situ on reactor components in the field. (ERA citation 03:047433)

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