陈宗欢,刘雪凇,杨德锋,王炳衡,高桂玲.球墨铸铁乏燃料贮运容器屏蔽研究[J].包装工程,2025,(3):294-299.
CHEN Zonghuan,LIU Xuesong,YANG Defeng,WANG Bingheng,GAO Guiling.Shielding Research of Ductile Cast Iron Spent Fuel Transport and Storage Container[J].Packaging Engineering,2025,(3):294-299. |
| 球墨铸铁乏燃料贮运容器屏蔽研究 |
| Shielding Research of Ductile Cast Iron Spent Fuel Transport and Storage Container |
| 投稿时间：2024-09-09 |
| DOI：10.19554/j.cnki.1001-3563.2025.03.035 |
| 中文关键词: 球墨铸铁 乏燃料贮运容器 源项 辐射屏蔽 |
| 英文关键词: ductile cast iron spent fuel transport and storage container source term radiation shielding |
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| 中文摘要: |
| 目的 瞄准我国未来乏燃料运输和贮存需求，进行容器辐射屏蔽设计关键问题研究，为研制具有安全性和经济性的球墨铸铁乏燃料贮运容器奠定基础。方法 对装载的乏燃料组件进行源项分析，分析关键贡献核素及组件冷却时间对源项的影响。结合源项特征及中子散射特性进行屏蔽材料选型，并研究中子屏蔽材料制造公差对屏蔽的影响。结果 中子源项的主要贡献核素为244Cm，占90%，能量主要在1~2 MeV，且不会随着冷却时间增加而快速减少;活化源项的主要来源为基体材料活化产生的60Co，随冷却时间增加而显著降低。综合容器的源项及热工特性，选取含铅聚乙烯作为中子屏蔽材料，并对制造公差提出了要求。结论 研究成果可用于球墨铸铁乏燃料贮运容器的辐射屏蔽设计，提升容器的屏蔽性能和装载能力，并进一步提升球墨铸铁乏燃料贮运容器的安全性和经济性。 |
| 英文摘要: |
| In response to China's future requirements for the transportation and storage of spent fuel, the work aims to explore investigate key issues in radiation shielding design of containers so as to provide a foundation for the development of a safe and cost-effective ductile cast iron spent fuel transport and storage container. A source term analysis was conducted for the loaded spent fuel assemblies, examining the impact of key contributing nuclides and the cooling time of the assemblies on the source term. Further, shielding material selection was carried out by considering the characteristics of the source term and neutron scattering properties, and the impact of manufacturing tolerances in neutron shielding materials on shielding effectiveness was studied. The results indicated that the main contributor to the neutron source term was 244Cm, accounting for 90%, with the energy primarily in the range of 1 MeV to 2 MeV, and it did not decrease rapidly with the increase of cooling time. The primary source of the activation source term was 60Co produced by the activation of matrix materials, which significantly decreased with the increase of cooling time. Considering the source term and thermal characteristics of the container, lead-polyethylene was selected as the neutron shielding material, and requirements for manufacturing tolerances were proposed. In conclusion, the research findings can be applied to the radiation shielding design of ductile cast iron spent fuel transport and storage containers, enhancing their shielding performance and loading capacity, and further improving the safety and cost-effectiveness of ductile cast iron spent fuel transport and storage containers. |
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