摘要
本文针对兼顾嬗变和产氚的铅合金冷却加速器驱动次临界反应堆ADS-T(ADS-Tritium),采用自主研发的大型集成多功能中子学计算与分析软件系统VisualBUS4.2和混合评价核数据库HENDL3.0,对散裂中子能量、产氚材料中6 Li丰度、结构钢材料、初始keff、中子能谱以及产氚组件摆放方式等产氚条件进行了敏感性分析。最后本文给出了年产氚千克级的ADS-T中子学初步方案,提供了一种有吸引力的氚生产途径。
In this paper, by using self-developed multi-functional 4D neutronics simulation system VisualBUS4. 2 and hybrid evaluated nuclear data library HENDL3.0, sensitivity analysis on spallation neutron energy, abundance of eLi in tritium breeding material, structural steel, initial keff, neutron energy spectrum as well as the placement of tritium production assembly was performed for lead-alloy cooled accelerator driven subcritical nuclear waste transmutation and tritium production reactor ADS-T （ADS- Tritium）. Finally, preliminary neutronics options of ADS-T were given, an attractive tritium production pathway was provided.
出处
《核科学与工程》
CSCD
北大核心
2013年第2期175-179,193,共6页
Nuclear Science and Engineering
基金
国家自然科学基金-加速器驱动次临界堆瞬态安全过程与影响机理研究(91026004)
中国科学院战略性先导科技专项(XDA03040000
XDA03040100)
关键词
加速器驱动
次临界反应堆
产氚
嬗变
中子学
accelerator driven
subcritical reactor
tritium production
transmutation
neutronics
