首页> 外文会议>ASME Pressure Vessels Piping Conference >ADDRESSING NRC CONCERNS REGARDING PROPOSED CC N-830: DIRECT USE OF FRACTURE TOUGHNESS FOR FLAW EVALUATIONS OF PRESSURE BOUNDARY MATERIALS IN CLASS 1 FERRITIC STEEL COMPONENTS
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ADDRESSING NRC CONCERNS REGARDING PROPOSED CC N-830: DIRECT USE OF FRACTURE TOUGHNESS FOR FLAW EVALUATIONS OF PRESSURE BOUNDARY MATERIALS IN CLASS 1 FERRITIC STEEL COMPONENTS

机译:针对CC N-830提案提出的NRC关注:直接使用断裂韧性对1类铁素体钢成分的压力边界材料进行过时的评估

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Section XI of the ASME Boiler and Pressure Vessel Code provides K_(Ic) and K_(Ia) fracture toughness models for ferritic steels. These models are based on linear elastic fracture mechanics methods and were initially developed in the 1970s; they remain largely unchanged since that time. Recently, a modification to Code Case (CC) N-830 has been proposed to provide alternative fracture toughness models for use in the flaw evaluation methodologies of ASME Section XI Nonmandatory Appendices A and K. The integrated models contained in proposed Code Case revision predict the mean trends and scatter of the fracture toughness behavior of ferritic steels throughout the temperature range from the lower shelf to the upper shelf. These models include the transition fracture toughness Master Curve and crack arrest master curve approaches that describe the temperature dependence and scatter in K_(Jc) and K_(Ia), respectively in the lower transition temperature region. Also included is a model describing the temperature dependence and scatter of K_(Ic) on the upper shelf. Finally, linkage models quantify the inter-relationships between these toughness metrics and how they change due to the irradiation-induced hardening. Together, these models describe the temperature dependence and scatter of fracture toughness initiation and arrest behavior for all ferritic reactor pressure vessel (RPV) steels from lower shelf through transition to the upper shelf, all indexed to a single parameter: T_0, In late 2017 the Electric Power Research Institute (EPRI) published a report, MRP-418, providing the technical basis for these revisions to CC N-830. Nuclear Regulatory Commission (NRC) staff review of the revised Code Case and MRP-418 resulted in substantive questions regarding validation and range of applicability of the various toughness models. An on-going effort addresses these concerns, and a revision to MRP-418 scheduled for publication later in 2019 will summarize that work. This paper describes the efforts of the WGFE CC-N-830 group to respond to the NRC's comments, and summarizes responses to some of the comments.
机译:《 ASME锅炉和压力容器规范》第XI节提供了铁素体钢的K_(Ic)和K_(Ia)断裂韧性模型。这些模型基于线性弹性断裂力学方法,最初是在1970年代开发的。自那时以来,它们基本上保持不变。最近,已提出对Code Case(CC)N-830的修改,以提供替代的断裂韧性模型,用于ASME第XI节非强制性附录A和K的缺陷评估方法。拟议Code Case修订版中包含的集成模型可以预测在从下层架到上层架的整个温度范围内,铁素体钢的断裂韧性行为的平均趋势和散布。这些模型包括过渡断裂韧性主曲线和裂纹止裂主曲线方法,分别描述了较低过渡温度区域中K_(Jc)和K_(Ia)的温度依赖性和分散性。还包括一个描述温度依赖性和K_(Ic)在上层架子上的散布的模型。最后,链接模型量化了这些韧性度量之间的相互关系,以及由于辐射诱导的硬化它们如何变化。这些模型共同描述了所有铁素体反应堆压力容器(RPV)钢从下层架到上层架的转变对温度的依赖性以及断裂韧性的起始和停止行为的散布,所有这些指数均指向一个参数:T_0,2017年末电力研究所(EPRI)发布了一份报告MRP-418,为CC N-830的这些修订提供了技术基础。核监管委员会(NRC)对修订后的规范案例和MRP-418进行的人员审查导致了关于各种韧性模型的验证和适用范围的实质性问题。正在进行的工作解决了这些问题,计划于2019年晚些时候发布的MRP-418修订版将总结该工作。本文介绍了WGFE CC-N-830小组对NRC意见做出的回应,并总结了对其中一些意见的回应。

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