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Detailed SCALE Dose Rate Evaluations for a Consolidated Interim Spent Nuclear Fuel Storage Facility

机译:合并的临时核燃料存储设施的详细SCALE剂量率评估

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摘要

A proposed CISF was modeled in detail using SCALE 6.2.1 to determine the radiation dose map of the surrounding areas of the facility and determine the location of the controlled area boundary based on 10 CFR 72.104 requirements. The spatial dose rate distribution was determined as the total dose rate contributions by each of the 467 storage casks comprising the CISF. A rectangular boundary outside of which no dose rate exceeds 25 mrem/yr has the dimensions of 1.25 km × 1.25 km. It denotes the smallest rectangle that could serve as the controlled area boundary. The results (dose map) show the unique capability of the SCALE code system for a high-resolution radiation dose simulation of a large SNF storage facility.
机译:使用SCALE 6.2.1对拟议的CISF进行了详细建模,以确定设施周围区域的辐射剂量图,并根据10 CFR 72.104的要求确定受控区域边界的位置。将空间剂量率分布确定为包含CISF的467个存储桶中的每个的总剂量率贡献。没有剂量率超过25 mrem / yr的矩形边界的尺寸为1.25 km×1.25 km。它表示可以用作受控区域边界的最小矩形。结果(剂量图)显示了SCALE代码系统对大型SNF存储设施进行高分辨率辐射剂量模拟的独特功能。

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    《Transactions of the American nuclear society》 |2018年第6期|765-768|共4页
  • 作者单位

    Oak Ridge National Laboratory 1 Bethel Valley Road, Oak Ridge, Term., 37831, United States;

    Oak Ridge National Laboratory 1 Bethel Valley Road, Oak Ridge, Term., 37831, United States;

    Oak Ridge National Laboratory 1 Bethel Valley Road, Oak Ridge, Term., 37831, United States;

    Oak Ridge National Laboratory 1 Bethel Valley Road, Oak Ridge, Term., 37831, United States;

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