综述了在乏燃料运输容器包容系统安全分析中使用的各类核素释放份额来源、取值和保守性分析,为乏燃料运输容器的研发提供参考。概述了国际上涉及核素释放份额的技术标准和研究报告,按照放射性核素的种类进行了分类总结,并结合相关文献分析了各类核素的释放份额数据的保守性。现有资料中核素的释放份额数据基本都由试验测定,但由于适用情景的不同,以及对试验测得数据处理方法上的差异,不同报告中对同一种核素的释放份额的取值可能有所不同。进行商用乏燃料运输容器包容系统安全分析时,ISO 12807以及ANSI N14.5规定的计算流程、释放份额数据均是可接受的,相比之下ANSI N14.5的假设更加保守。假定放射性气体的释放份额为0.3、易挥发核素的释放份额为2×10-4、微型颗粒的释放份额为3×10-5,以及正常运输工况下积垢剥落比例为0.15,这样假定是有试验数据支持且能保证运输安全的。
Abstract
The work aims to summarize and discuss the sources, values, and conservativeness of radionuclide release fractions used in the safety analysis of containment systems for spent fuel transportation casks so as to provide a reference for research and development of spent fuel transportation casks. Initially, the technical standards and research reports involving radionuclide release fractions internationally were outlined, and then classified by the types of radionuclides. Additionally, the conservativeness of radionuclide release fraction data was analyzed in conjunction with relevant literature. Most of release fractions of radionuclides were determined through experiments. However, due to differences in fuel conditions and methods used to process the experimental data, the release fraction values for same radionuclide may vary across different reports. When conducting safety analysis for the containment system of casks used in the transport of commercial spent fuel, the calculation processes and release fraction data stipulated in ISO 12807 and ANSI N14.5 are all acceptable. In contrast, the assumptions of ANSI N14.5 are more conservative. It is assumed that the release fraction of fission gases is 0.3, the release fraction of volatiles is 2×10-4, the release fraction of fines is 3×10-5, and the fraction of crud that spalls-off of rods is 0.15 under normal transport conditions. These assumptions are supported by experimental data and can ensure transport safety.
关键词
包容系统 /
活度释放 /
释放份额
Key words
containment system /
activity release /
release fractions
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