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RESEARCH NEEDS FOR EXTENDED STORAGE OF USED NUCLEAR FUEL: CONTAINER AND OVERPACK

机译:使用核燃料扩展存储的研究需求:容器和外包装

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With the continuously escalating demand for longer term interim dry storage of spent nuclear fuel from light water reactors, coupled with the increasingly high-burnup levels of that fuel, comes the need to enhance the technical basis for such storage. In 2010, the Department of Energy initiated a program whose goal is to identify and study those technical issues requiring further research and development, focusing on the degradation processes that occur during normal and off-normal dry storage conditions. The program was initiated with a review of those features, events, and processes (FEPs) that could impact the five safety functions of the structures, systems, and components (SSCs) important to safety (ITS), namely: 1) thermal performance, 2) radiation protection, 3) confinement, 4) sub-criticality, and 5) retrievability. Review articles, presentations, NRC regulations, industry standards, and NRC safety analysis reports were consulted, and a consolidated FEPs list for normal and off-normal conditions was created for each SSC of a generic dry cask storage system. The SSCs included: 1) fuel, 2) cladding, 3) fuel assembly hardware, 4) fuel baskets, 5) neutron poisons, 6) neutron shields, 7) container, 8) overpack or storage module, 9) pad, and 10) monitoring systems. The resulting FEPs lists were then refined so as to include only those degradation mechanisms that may be impacted by increasingly long storage times, higher burnup, or that had other data needs for each SSC. A summary of the key degradation mechanisms for both the storage container and the concrete overpack/storage module, along with their relative research priority is presented in Tables I and II. The research priority was defined based upon the current state of knowledge in each area, the likelihood of occurrence, ease of remediation, and potential consequences. An overview of these mechanisms and their associated research needs, will be presented.
机译:随着从轻型水反应器的长期临时干燥储存的不断升级的需求,加上燃料越来越高的燃烧水平,有必要提高这种储存的技术基础。 2010年,能源部启动了一个计划,其目标是识别和研究需要进一步研发的技术问题,重点是在正常和非正常干燥储存条件下发生的降解过程。该计划是在审查这些功能,事件和流程(FEPS)的审查,这些功能可能会影响结构,系统和组件(SSCS)的五种安全功能,这对于安全(其),即:1)热性能, 2)辐射保护,3)限制,4)次临界度,5)可回收性。审查咨询文章,演示文稿,NRC法规,行业标准和NRC安全分析报告,并为通用干式储物系统的每个SSC创建了正常和离法条件的综合FEPS列表。的精原干细胞包括:1)燃料,2)包层,3)的燃料组件的硬件,4)燃料篮,5)中子毒物,6)中子屏蔽,7)容器,8)外包装或存储模块,9)垫,和10 )监测系统。然后改进所产生的FEPS列表,以便仅包括可能受到越来越长的存储时间,更高的燃烧,或者每个SSC的其他数据需求影响的那些降级机制。存储容器和混凝土超级包/存储模块以及其相对研究优先级的密钥劣化机制概述呈现在表I和II中。该研究的重点是基于知识的每个区域,发生的可能性,便于整治和潜在后果的当前状态来定义。将介绍这些机制及其相关研究需求的概述。

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