聚变-裂变混合堆三种嬗变包层中子学方案初步分析  

Preliminary analyses of neutronics schemes for three kinds waste transmutation blankets of fusion-fission hybrid

作　　者：张明春[1] 冯开明[1] 栗再新[1] 赵奉超[1] 

机构地区：[1]核工业西南物理研究院,成都610041

出　　处：《核聚变与等离子体物理》2012年第4期344-350,共7页Nuclear Fusion and Plasma Physics

摘　　要：采用球形托卡马克(ST)等离子体位形,对氦冷嬗变包层、钠冷嬗变包层、氟锂铍(FLiBe)熔盐冷嬗变包层三种嬗变包层中子学方案进行了初步计算分析,并就各自的中子学特性进行了比较。结果表明,从嬗变长寿命放射性锕系核素237Np的角度考量,FLiBe冷却嬗变包层的嬗变性能最优。对氦冷嬗变包层的计算结果表明,通过改变初装料时237Np在次锕系元素中的成分比例,可使包层在比较长的运行时间(9.62年)内,保持稳定有效增殖系数、稳定功率、稳定产氚率。The neutronics schemes of the helium-cooled waste transmutation blanket, sodium-cooled waste transmutation blanket and FLiBe-cooled waste transmutation blanket were preliminarily calculated and analysed by using the spheroidal tokamak （ST） plasma configuration. The neutronics properties of these blankets＇ were compared and analyzed. The results show that for the transmutation of 237Np, FLiBe-cooled waste transmutation blanket has the most superior transmutation performance. The calculation results of the helium-cooled waste transmutation blanket show that this transmutation blanket can run on a steady effective multiplication factor （kerr）, steady power （P）, and steady tritium production rate （TBR） state for a long operating time （9.62 years） by change 237Np＇s initial loading rate of the minor actinides （MA）.

关 键 词：聚变 嬗变 包层 中子学 

分 类 号：TL46[核科学技术—核技术及应用]