聚变驱动次临界堆双冷嬗变包层中子学设计与分析  

Neutronic design and analysis of dual-cooled waste transmutation blanket for the fusion driven sub-critical system

作　　者：郑善良[1] 吴宜灿[1] 高纯静[1] 许德政[1] 李静惊[1] 朱晓翔[1] 

机构地区：[1]中国科学院等离子体物理研究所,安徽合肥230031

出　　处：《核科学与工程》2004年第2期164-170,共7页Nuclear Science and Engineering

基　　金：国家自然科学基金资助项目(10175067;10175068;103750607);中科院知识创新工程项目资助

摘　　要：对聚变驱动次临界堆的多功能双冷核废料嬗变包层进行了中子学设计和分析,设计目标是:①氚和钚燃料自持;②较少的初装料得到较高的废料嬗变率。使用的程序是自主开发的多功能中子输运/燃耗/优化程序VisuaIBUs1.0,相应的数据库是175群中子/42群光子的多群数据库HENDL1.0/MG。Neutronics design and analysis of dual-cooled multi-functional waste transmutation blanket(DWTB) for the fusion driven sub-critical system (FDS) are performed to ensure the system be able to meet the requirements of fuel-sufficiency and more waste transmutation ratio with low initial loading fuel inventory, which is based on 1-D burn-up calculations with home-developed code Visual BUS and the multi-group (175 neutron groups - 42 Gamma groups coupled) data library HENDL1. 0/MG (Hybrid Evaluated Nuclear Data Library).

关 键 词：聚变驱动 次临界堆 双冷嬗变 中子学设计 包层 

分 类 号：TL411.1[核科学技术—核技术及应用] TL613