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基于乏燃料贮存格架临界安全的硼铝合金材料中子吸收检测数据统计方法研究
Statistical method for neutron absorption test data of boron aluminum alloy based on critical safety of spent fuel storage grillwork
【机构】 中国原子能科学研究院;
【摘要】 作为乏燃料临界控制材料含硼铝基材料(硼铝合金材料)的硼-10面密度是衡量材料中子吸收能力的标准,本文介绍了中子衰减方法测量乏燃料贮存格架所用硼铝合金材料的硼-10面密度及均匀性检测方法,为了保证检测结果符合临界安全的条件,需要对所有测点的中子穿透率数据进行统计学分析,按一定置信度和误差要求判断是否满足规格书中要求的硼-10面密度值。
【Abstract】 As the critical control material of spent fuel, the boron-10 areal density of Boron-containing aluminumbased materials(Boron-Al alloy material)is the standard to measure the neutron absorption capacity of materials. This paper introduces the neutron attenuation method to measure the boron-10 areal density and uniformity of boron aluminum alloy material used in spent fuel storage grillwork. In order to ensure that the test results meet the critical safety conditions, it is necessary to measure the neutron penetration rate of all test points. The data were statistically analyzed to determine whether the boron-10 areal density meets the requirements of the specification according to certain confidence and error requirements.
【Key words】 neutron penetration rate; boron-10 areal density; one sided tolerance factors; standard sample;
- 【会议录名称】 中国核科学技术进展报告(第七卷)——中国核学会2021年学术年会论文集第9册(核技术经济与管理现代化分卷、知识产权分卷、核电子学与核探测技术分卷、核测试与分析分卷)
- 【会议名称】中国核学会2021年学术年会
- 【会议时间】2021-10-19
- 【会议地点】中国山东烟台
- 【分类号】TG146.21;TM623
- 【主办单位】中国核学会