加速器驱动核废料嬗变次临界堆中子学初步设计分析

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650 kg/a,同时满足能量自持并具备约1000 MW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 design,liquid lead-bismuth eutectic (LBE) and transuranic metallic dispersion fuel were used as coolant and 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.