10MW高温气冷堆乏燃料元件的贮存及其安全分析  

Safety analysis of spent fuel element storage in 10MW high temperature gascooled reactor

作　　者：肖宏伶[1] 刘继国[1] 

机构地区：[1]清华大学核能技术设计研究院

出　　处：《清华大学学报（自然科学版）》2001年第10期49-51,共3页Journal of Tsinghua University(Science and Technology)

基　　金：国家"八六三"高技术项目 ( 86 3-6 14 -0 2 -0 7)

摘　　要：10 MW高温气冷堆 (HTR- 10 )在设计寿命内共卸出约 9万个乏燃料元件 ,其放射性裂变产物的活度高达 1.0× 10 1 6Bq,必须妥善处置。HTR- 10乏燃料元件卸在密封和屏蔽的容器中 ,每个容器可以接受 2 0 0 0个乏燃料元件 ,这些容器固定在反应堆建筑物的最底层的混凝土井内 ,在贮存库内采取通风冷却。文中对放射性核素释放 ,临界安全和辐射屏蔽等方面进行了分析 。Approximately 90000 spent fuel elements will be discharged from a 10MW high temperature gascooled reactor (HTR10) in its lifetime. The activity of the radioactive fission products in these spent fuel elements will reach 1.0×10 16 Bq, so these spent fuel elements should be properly managed. HTR10 spent fuel elements will be discharged into leadsteel containers, with each container designed to receive 2000 fuel elements. These containers will be stored in a concrete compartment inside the reactor building and cooled by air. This paper analyzes the release of the radioactive nuclides, the critical safety parameters and the irradiation shielding. The results show that the safety requirements can be met in the HTR10 spent fuel element storage compartment.

关 键 词：高温气冷堆 乏燃料元件 贮存 安全分析 HTR-10 通风冷却 放射性裂变产物 

分 类 号：TL424[核科学技术—核技术及应用] TL352