核电站乏燃料中Np-237和Am-243的含量预测与分析  

Prediction and Analysis of Content of Np-237 and Am-243 in Nuclear Power Plants,Spent Fuel

作　　者：周敏兰[1,2] 刘义保[1] 王爱星[1] 钮云龙[1,2] 吴思远[1,2] 

机构地区：[1]东华理工大学核技术应用教育部工程研究中心,南昌330013 [2]东华理工大学核工程地球物理学院,南昌330013

出　　处：《能源研究与管理》2014年第2期19-22,共4页Energy Research and Management

基　　金：江西省高等学校科技落地计划项目(KJLD12076)

摘　　要：应用ORIGEN2.1程序对1座功率为1000MW核电机组运行3年后乏燃料次锕系核素(MA)中的NP-237和Am-243的累计量做了预测;并分析核电运行3年后,该2种核素经过短期和长期衰变后的含量变化趋势。为乏燃料的后处理提供有价值的参考。ORIGEN2.1 program was used to predict the cumulative amount of NP-237 and Am-243 of minor actinides in spent fuel after a power of 1000 MW nuclear power units operating three year, and analysis the changes of the content of two nuclides that decayed short-term and long-term after the nuclear power units operating three year were analyzed. As to provide valuable references in the reprocessing of the spent fuel.

关 键 词：核电 乏燃料 ORIGEN2 1 次锕系核素 

分 类 号：TL24[核科学技术—核燃料循环与材料]