首页> 外文会议>International conference on environmental degradation of materials in nuclear power systems-water reactors >EVALUATION OF STRATEGIES FOR OBTAINING HIGH FLUENCE MATERIALS TO ASSESS IRRADIATION-ASSISTED DEGRADATION OF PWR INTERNALS
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EVALUATION OF STRATEGIES FOR OBTAINING HIGH FLUENCE MATERIALS TO ASSESS IRRADIATION-ASSISTED DEGRADATION OF PWR INTERNALS

机译:获得高流量材料策略评估PWR内部人员辐照降解的策略

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One of the key technical issues for nuclear power plant operation up to 80 years is high-fluence irradiation-assisted degradation (IAD) of reactor internals composed of austenitic stainless steels. High-fluence IAD may become more severe at neutron damage levels approaching or exceeding 80 displacements per atom (dpa) accumulated during operation up to 80 years. There are several potential approaches for developing a technical basis related to IAD to support extended reactor operation up to 80 years. The approaches considered in this paper include using data from existing research programs and generating additional data from ion irradiation, fast reactor irradiation, near-light water reactor (LWR) spectrum irradiation, and near-LWR spectrum further irradiation of harvested ex-plant materials. For each of the potential approaches considered, this paper summarizes both the technical and non-technical benefits and drawbacks. Technical considerations are associated with the representativeness of the approach to the actual irradiation exposure in a PWR, while non-technical considerations include level of effort, schedule and project complexity.
机译:核电厂运行的关键技术问题之一,高达80年是由奥氏体不锈钢组成的反应器内部的高流量辐照辅助降解(IAD)。高流量IAD在空中损伤水平下可能变得更严重或超过80次在运行期间累积的80个位移,长达80年。开发与IAD相关的技术基础有几种潜在方法,以支持高达80年的扩展反应堆操作。本文考虑的方法包括使用现有研究计划的数据,并从离子辐射,快速反应器辐射,近光水反应器(LWR)谱辐射和接近-LWR光谱进一步照射收获的前植物材料的附加数据。对于所考虑的每种潜在方法,本文总结了技术和非技术效益和缺点。技术考虑与PWR中实际辐射暴露的方法的代表性相关,而非技术考虑包括努力,进度和项目复杂程度。

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