加速器驱动核废料嬗变次临界堆中子学初步设计分析  

Preliminary Neutronics Design Analysis on Accelerator Driven Subcritical Reactor for Nuclear Waste Transmutation

作　　者：陈忠[1,2] 蒋洁琼[1] 王明煌[1] 曾勤[1] 柏云清[1] 吴宜灿[1,3] FDS团队 

机构地区：[1]中国科学院核能安全技术研究所,安徽合肥230031 [2]西南科技大学国防科技学院,四川绵阳621000 [3]中国科学技术大学,安徽合肥230027

出　　处：《核科学与工程》2013年第2期180-185,共6页Nuclear Science and Engineering

基　　金：国家自然科学基金重大研究计划重点支持项目(No.91026004);中国科学院战略性先导科技专项"未来先进核裂变能-ADS嬗变系统"(XDA03040000;XDA03040100)

摘　　要：针对铅合金冷却加速器驱动核废料嬗变次临界堆ADS-NWT,以次锕系核素(MA)嬗变性能为评价指标,开展了ADS-NWT中子学初步设计分析。设计采用液态铅铋作为冷却剂,选择超铀弥散金属燃料,使用大型集成中子学计算分析系统VisualBUS和混合评价核数据库HENDL进行计算分析。结果表明:当MA/Pu体积比为7∶3时全堆对MA的嬗变率可达约650kg/a,同时满足能量自持并具备约1 000MW能量输出,较深的次临界度和负反应性系数表明ADS-NWT具有良好的固有安全性。By taking minor actinides （MA） transmutation performance as evaluation index, preliminary neutronics design analyses were performed on ADS-NWT which is a lead-alloy cooled accelerator driven subcritical reactor for nuclear waste transmutation. In the specific dispersion fuel design, liquid were used as lead-bismuth coolant and eutectic （LBE） and transuranic metallic a fuel of ADS-NWT, respectively. The neutronics calculations and analyses were performed by using CAD-based multifunctional 4D neutronics radiation simulation system named VisualBUS and the nuclear data library HENDL （Hybrid Evaluated Nuclear Data Library） . The preliminary results showed that based on specific deign of MA/Pu volume ratio of 7 ： 3, the transmutation rate of MA was approximately 650 kg/a, the high thermal reactor power output was -1 000 MW when energy self-sustaining was satisfied and relatively deep subcriticality and negative reactivity coefficients made sure of good inherent safety of ADS-NWT.

关 键 词：加速器驱动次临界堆 嬗变 中子学 

分 类 号：TL32[核科学技术—核技术及应用]