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 Rpt. No. 45 July-Sept. 1978
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Reactor Primary Coolant System Pipe Rupture Study Method for Detection of Sensitization in Stainless Steel Progress Rpt. No. 45 July-Sept. 1978

机译:反应堆一次冷却系统管道破裂研究方法检测不锈钢中的敏化过程Rpt。 7月45日至9月1978年

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摘要

A program is in progress to develop a quantitative method [Electrochemical Potentiokinetic Reactivation (EPR)] for nondestructively measuring the degree of sensitization in Type-30^ 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.

著录项

  • 作者

    W. L. Clarke;

  • 作者单位
  • 年度 1979
  • 页码 1-33
  • 总页数 33
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 工业技术;
  • 关键词

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