Nuclear criticality safety analysis in dissolving process of spent fuel reprocessing

被引:0
作者
Liu, Ying-Yu [1 ]
Luo, Zhi-Wen [1 ]
Liu, Zhen-Hua [1 ]
机构
[1] China Institute of Atomic Energy
来源
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | 2013年 / 47卷 / 08期
关键词
Dissolver; Nuclear criticality safety; Spent fuel reprocessing;
D O I
10.7538/yzk.2013.47.08.1375
中图分类号
学科分类号
摘要
A rational space distribution model for spent fuel element dissolving at each stage of process in reprocessing plant was formulated. The nuclear criticality on safety issue was studied by calculating numerical model on the process of spent fuel dissolution in consideration of the given plant arrangement. An assessment of the influence of several main critical parameters to the plant safety was given. The calculation results show that the most dangerous status occurs at the initial stage of dissolution when fissile nuclide transforms under ideal conditions. A negative influence to the system is indicated by the increase of temperature and concentration of nitric acid, and the effect is less than 4%. System safety can be improved greatly by the addition of neutron poison or the application of fuel burnup credit, and the effect reaches 30%.
引用
收藏
页码:1375 / 1379
页数:4
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