Analysis of Th-U and U-Pu fuel cycle in a 2 500 MWth molten chloride salt fast reactor
NUCLEAR ENERGY SCIENCE AND ENGINEERING|更新时间:2024-10-25
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Analysis of Th-U and U-Pu fuel cycle in a 2 500 MWth molten chloride salt fast reactor
“In the field of nuclear energy, researchers have studied the neutron properties of Th-U and U-Pu cycles based on a 2500MWth chloride fast reactor, and found that the TRU+Th cycle has superior self-sustaining proliferation performance and high transmutation performance.”
NUCLEAR TECHNIQUESVol. 43, Issue 11, (2020)
作者机构:
1.中国科学院上海应用物理研究所 上海 201800
2.中国科学院先进核能创新研究院 上海 201800
3.中国科学院大学 北京 100049
作者简介:
LI Xiaoxiao, female, born in 1984, graduated from Institute of High Energy Physics of Chinese Academy of Sciences with a doctoral degree in 2011, focusing on the research of neutronics design of molten salt reactor and the associated nuclear fuel cycle
MA Yuwen, E-mail: mayuwen@sinap.ac.cn
CHEN Jingen, E-mail: chenjingen@sinap.ac.cn
基金信息:
the Young Potential Program of Shanghai Institute of Applied Physics, Chinese Academy of Sciences(Y955051031)
LI Xiaoxiao,YU Chenggang,MA Yuwen,et al.Analysis of Th-U and U-Pu fuel cycle in a 2 500 MWth molten chloride salt fast reactor[J].NUCLEAR TECHNIQUES,2020,43(11):66-75.
LI Xiaoxiao,YU Chenggang,MA Yuwen,et al.Analysis of Th-U and U-Pu fuel cycle in a 2 500 MWth molten chloride salt fast reactor[J].NUCLEAR TECHNIQUES,2020,43(11):66-75. DOI: 10.11889/j.0253-3219.2020.hjs.43.110601.
Analysis of Th-U and U-Pu fuel cycle in a 2 500 MWth molten chloride salt fast reactor