目的 针对国内核电站高燃耗、短冷却时间乏燃料组件的运输需求,为突破原有容器装载能力与衰变热限值的瓶颈,开展CNSC-24S乏燃料运输容器屏蔽性能优化研究。方法 基于GB 11806—2019《放射性物品安全运输规程》,采用ICRP 116最新通量-剂量转换系数,建立24组与20组装载方案的蒙特卡罗屏蔽分析模型;通过对比ICRP 74与ICRP 116通量-剂量转换系数的差异,结合导热屏蔽件布置与吊篮上部补偿屏蔽设计,对常规运输条件容器外部各位置处的剂量率进行评估。结果 采用ICRP 116系数计算时,容器表面最大剂量率由2.45 mSv/h降至1.67 mSv/h,距车辆外侧面2 m处剂量率由0.126 mSv/h降至0.087 5 mSv/h,满足国家标准;20组装载方案配合导热屏蔽件可安全运输单组衰变热1.2 kW、冷却时间7.4 a的乏燃料组件;吊耳处补偿屏蔽将局部剂量率从2.12 mSv/h降至1.33 mSv/h,消除了操作人员的过量受照风险。结论 CNSC-24S容器通过优化通量-剂量转换系数选取、装载方案及局部屏蔽结构,实现了最大装载24组、总衰变热24 kW的乏燃料安全运输,各项辐射指标均满足GB 11806—2019的相关要求,有效提升了国产化乏燃料运输容器的技术水平与市场竞争力。
Abstract
The work aims to study the shielding performance optimization of CNSC-24S spent fuel transport casks to overcome the insufficient loading capacity, decay heat limits of existing spent fuel transport casks and meet the transportation requirements for high-burnup, short-cooling-time spent fuel assemblies from domestic nuclear power plants. Based on GB 11806-2019 "Regulations for the Safe Transport of Radioactive Material", the latest ICRP 116 flux-to-dose conversion coefficients were employed to establish Monte Carlo shielding analysis models for both 24-assembly and 20-assembly loading configurations. By comparing the differences between ICRP 74 and ICRP 116 flux-to-dose coefficients, and incorporating the arrangement of heat-conducting shields and compensatory shielding design at the upper basket, dose rate assessments were conducted for various external positions of the cask under normal transportation conditions. When calculated using ICRP 116 coefficients, the maximum surface dose rate of the cask decreased from 2.45 mSv/h to 1.67 mSv/h, and the dose rate at 2 m from the vehicle exterior decreased from 0.126 mSv/h to 0.087 5 mSv/h, meeting national standards. The 20-assembly loading scheme, combined with heat-conducting shields, enabled safe transportation of spent fuel assemblies with individual decay heat of 1.2 kW and cooling time of 7.4 years. The compensatory shielding at the trunnion area reduced the local dose rate from 2.12 mSv/h to 1.33 mSv/h, eliminating the risk of excessive radiation exposure for operators. Through optimization of flux-to-dose conversion coefficient selection, loading configurations, and local shielding structures, the CNSC-24S cask achieves safe transportation of spent fuel with a maximum capacity of 24 assemblies and total decay heat of 24 kW. All radiation indicators satisfy relevant requirements of GB 11806-2019, effectively enhancing the technical capability and market competitiveness of domestically produced spent fuel transport casks.
关键词
乏燃料运输容器 /
屏蔽设计 /
通量-剂量转换系数
Key words
spent fuel transport cask /
shielding design /
flux-to-dose conversion coefficient
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