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NRC Welding Residual Stress Validation Program International Round Robin Program and Findings

机译：NRC焊接残余应力验证计划国际Round Robin计划和调查结果

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The U.S. Nuclear Regulatory Commission (NRC) and the Electric Power Research Institute (EPRI) are working cooperatively under a memorandum of understanding to validate welding residual stress (WRS) predictions in pressurized water reactor (PWR) primary cooling loop components containing dissimilar metal (DM) welds. These stresses are of interest as DM welds in PWRs are susceptible to primary water stress corrosion cracking (PWSCC) and tensile weld residual stresses are the primary driver of this degradation mechanism. The NRC/EPRI weld residual stress (WRS) analysis validation program consists of four phases, with each phase increasing in complexity from laboratory size specimens to component mock-ups and cancelled-plant material. This paper discusses Phase 2 of the WRS characterization program involving an international round robin analysis project in which participants analyzed a prototypic reactor coolant pressure boundary component. Mock-up fabrication, WRS measurements and comparison with predicted stresses through the DM weld region are described. The results of this study show that, on average, analysts can develop WRS predictions that are a reasonable estimate for actual configurations as quantified by measurements. However, the scatter in predicted results from analyst to analyst can be quite large. For example, in this study, the scatter in WRSs through the centerline of the main DM weld (prior to stainless steel weld application) predicted by analysts is approximately +/- 200 to 300 MPa at 3 standard deviations for axial stresses and +/- 300 to 400 MPa at 3 standard deviations for hoop stresses. Sensitivity studies that vary important parameters, such as material hardening behavior, can be used to bound such large variations.
机译：美国核监管委员会（NRC）和电力研究所（EPRI）正在根据一份谅解备忘录进行合作，以验证压水堆（PWR）包含异种金属（DM）的主要冷却回路部件中的焊接残余应力（WRS）预测）焊缝。这些压力是令人关注的，因为PWR中的DM焊缝易受主要水应力腐蚀开裂（PWSCC）的影响，而拉伸焊缝残余应力是此降解机理的主要驱动力。 NRC / EPRI焊接残余应力（WRS）分析验证程序包括四个阶段，每个阶段的复杂性从实验室大小的样本到组件模型和取消的工厂材料，其复杂性都在增加。本文讨论了WRS表征计划的第二阶段，该阶段涉及一个国际循环分析项目，参与者在其中分析了原型反应堆冷却剂压力边界分量。描述了模型制造，WRS测量以及与通过DM焊接区域的预测应力的比较。这项研究的结果表明，平均而言，分析人员可以开发WRS预测，这是对通过测量量化的实际配置的合理估计。但是，分析师之间的预测结果差异可能很大。例如，在本研究中，分析人员预测，在3个标准偏差的轴向应力下，WRS在主DM焊缝（在不锈钢焊缝应用之前）通过中心线的中心线的散布约为+/- 200至300 MPa。 300到400 MPa，环向应力有3个标准偏差。改变重要参数（例如材料硬化行为）的敏感性研究可用于限制如此大的变化。

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