首页> 外文会议>American Nuclear Society;International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors >TECHNICAL BASIS FOR ASME SECTION XI CODE CASE FOR STRESS CORROSION CRACK GROWTH RATE EVALUATIONS FOR ALLOY 690 AND ASSOCIATED WELDS
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TECHNICAL BASIS FOR ASME SECTION XI CODE CASE FOR STRESS CORROSION CRACK GROWTH RATE EVALUATIONS FOR ALLOY 690 AND ASSOCIATED WELDS

机译:合金690及相关焊缝应力腐蚀裂纹扩展速率评估的ASME第XI代码案例的技术基础

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Alloy 690 and its associated weld metals (Alloys 52, 152, and variants) have been used in service as replacement materials for Alloy 600 and its associated weld metals (Alloys 82, 182, and 132) since the materials were accepted in the ASME Boiler and Pressure Vessel Code in 1989. To date, there have been no reported incidents of primary water stress corrosion cracking (PWSCC) in these replacement materials in operating plants. While this is a strong indicator that the Alloy 690 materials are resistant to PWSCC, in closely controlled laboratory experiments, PWSCC in these materials has been induced. Therefore, a need exists to characterize the PWSCC crack growth rates in Alloy 690 materials to evaluate possible cases where a) a flaw initiates in these materials in service, b) crack growth extends into these materials from existing flaws occurring in adjacent susceptible material, or c) a manufacturing defect is conservatively interpreted as PWSCC. This paper provides the technical basis for incorporating such a crack growth rate evaluation method into a Code Case in the ASME Boiler and Pressure Vessel Code. This method was developed based on PWSCC data obtained from laboratories around the world, which were compiled and screened for data quality and plant applicability by an expert panel. This paper provides a summary of the effort to develop the factor of improvement approach, which bases the predicted PWSCC growth rates of Alloy 690 and its welds on that of Alloy 600 and its welds, respectively, under similar conditions.
机译:自从ASME锅炉接受该材料以来,合金690及其相关的焊接金属(合金52、152和变体)已用作合金600及其相关的焊接金属(合金82、182和132)的替代材料。和1989年的《压力容器法》。迄今为止,尚未有报道在运营工厂的这些替代材料中发生一次水应力腐蚀开裂(PWSCC)的事件。尽管这是一个强有力的指标,表明690合金材料具有抗PWSCC的性能,但在严格控制的实验室实验中,已诱导了这些材料中的PWSCC。因此,需要表征690合金材料中的PWSCC裂纹扩展速率,以评估以下情况的可能情况:a)使用中的这些材料中引发了缺陷; b)裂纹从相邻易受影响材料中存在的缺陷扩展到了这些材料中;或者c)保守地将制造缺陷解释为PWSCC。本文为将这种裂纹扩展率评估方法纳入ASME锅炉和压力容器规范中的规范案例提供了技术基础。该方法是根据从世界各地实验室获得的PWSCC数据开发的,由专家小组对这些数据进行汇编和筛选,以确保数据质量和工厂适用性。本文概述了开发改进因子方法的工作,该方法基于在相似条件下,合金690及其焊缝的预测PWSCC增长率分别基于合金600及其焊缝的增长率。

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