Multi-Physics Model Development for Polonium Transport Behavior in a Lead-Cooled Fast Reactor

被引:3
|
作者
Lilin, Deng [1 ]
Yuqing, Wang [2 ]
Zian, Zhai [1 ]
Bochen, Huang [1 ]
Jiewei, Wu [2 ,3 ]
Jianbo, He [2 ]
Muyi, Ni [2 ,3 ]
机构
[1] Nucl Power Inst China, Sci & Technol Reactor Syst Design Technol Lab, Chengdu, Peoples R China
[2] Sun Yat Sen Univ, Sino French Inst Nucl Engn & Technol, Guangzhou, Peoples R China
[3] Inst Adv Sci Facil IASF, Shenzhen, Peoples R China
关键词
polonium; LBE; fast reactor; Gen-IV; nuclear safety; BISMUTH; SYSTEMS; REMOVAL;
D O I
10.3389/fenrg.2021.711916
中图分类号
TE [石油、天然气工业]; TK [能源与动力工程];
学科分类号
0807 ; 0820 ;
摘要
Po-210, a highly toxic element with strong volatility, is one of the main source terms of a Gen-IV lead-cooled fast reactor (LFR). Therefore, the radioactive safety caused by Po-210 has become an important topic in LFR-related research. In order to simulate the behavior of Po-210 in an LFR, this work developed a multi-physics model of an LFR from the perspective of radioactive transport. Considering the effects of nuclide decay, cover gas leakage, containment ventilation, and Po aerosol deposition, a comprehensive simulation was carried out to evaluate the sensitivity of those effects on the Po-210 distribution in detail. Preliminary results indicate that during normal operation, most of the Po-210 in the LBE exist in the form of PbPo, and around 10(-9) of Po-210 could evaporate from the LBE into the cover gas, and then further leak into the containment. In addition, even if the leakage rate of Po-210 in the cover gas into the containment is maintained at 5 parts per thousand per day, due to the deposition of Po aerosol, the Po-210 contamination on the inner surface of the containment is still below the radioactivity concentration limits.
引用
收藏
页数:9
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