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[期刊论文] 作者:Kun Yang,Wei Qin,Jin-Gen Chen,Xiang-Zhou Cai,, 来源:Nuclear Science and Techniques 年份:2016
Fertile fuel, such as thorium or depleted uranium, can be bred into fissile fuel and burnt in a breed-andburn(B&B) reactor. Modeling a full core with fertile fu...
[期刊论文] 作者:Xue-Chao Zhao,De-Yang Cui,Xiang-Zhou Cai,Jin-Gen Chen, 来源:核技术(英文版) 年份:2018
Accelerator-driven systems based on molten salt fuel have several unique advantages and features for advanced nuclear fuel utilization.The aim of this work was...
[期刊论文] 作者:Kun Yang,Wei Qin,Jin-Gen Chen,Xiang-Zhou Cai, 来源:核技术(英文版) 年份:2016
[期刊论文] 作者:Ya-Peng Zhang,Yu-Wen Ma,Jian-Hui Wu,Jin-Gen Chen,Xiang-Zhou Cai, 来源:核技术(英文版) 年份:2020
Heavy water-moderated molten salt reactors (HWMSRs) are novel molten salt reactors that adopt heavy water rather than graphite as the moderator while employing...
[会议论文] 作者:Na-na Guan,Jia-li Long,Ze-jun He,Xiang-zhou Cai,Yu-gang Ma, 来源:The 10th International Conference on Nucleus-Nucleus Collisi 年份:2009
[期刊论文] 作者:Xiao-Xiao Li,De-Yang Cui,Yu-Wen Ma,Xiang-Zhou Cai,Jin-Gen Chen, 来源:核技术(英文版) 年份:2019
To optimize the temperature coefficient of reactivity (TCR) for a graphite-moderated and liquid-fu-eled molten salt reactor, the effects of fuel salt compositio...
[期刊论文] 作者:Kun-Feng Ma,Cheng-Gang Yu,Xiang-Zhou Cai,Chun-Yan Zou,Jin-Gen Chen, 来源:核技术(英文版) 年份:2020
Herein, we assess the 129I transmutation capa-bility of a 2250-MWt single-fluid double-zone thorium molten salt reactor (SD-TMSR) by considering two meth-ods. O...
[期刊论文] 作者:De-Yang Cui,Shao-Peng Xia,Xiao-Xiao Li,Xiang-Zhou Cai,Jin-Gen Chen,, 来源:Nuclear Science and Techniques 年份:2017
The molten salt reactor(MSR), as one of the Generation Ⅳ advanced nuclear systems, has attracted a worldwide interest due to its excellent performances in safe...
[会议论文] 作者:Na-na Guan,Jia-li Long,Ze-jun He,Xiang-zhou Cai,Yu-gang Ma, 来源:The 10th International Conference on Nucleus-Nucleus Collisi 年份:2009
[期刊论文] 作者:Long He,Cheng-Gang Yu,Rui-Min Ji,Wei Guo,Ye Dai,Xiang-Zhou Cai, 来源:核技术(英文版) 年份:2019
A molten salt reactor (MSR) is one of the six advanced reactor concepts selected by the generation IV inteational forum because of its advantages of inherent sa...
[期刊论文] 作者:Xiao-Xiao Li,Yu-Wen Ma,Cheng-Gang Yu,Chun-Yan Zou,Xiang-Zhou Cai,Jin-Gen Chen, 来源:核技术(英文版) 年份:2018
With respect to a liquid-fueled molten salt reactor (MSR),the temperature coefficient of reactivity mainly includes the moderator temperature coefficient (MTC)...
[期刊论文] 作者:Bin Deng,Yong Cui,Jin-Gen Chen,Long He,Shao-Peng Xia,Cheng-Gang Yu,Fan Zhu,Xiang-Zhou Cai, 来源:核技术(英文版) 年份:2020
In the core of a molten salt fast reactor (MSFR), heavy metal fuel and fission products can be dissolved in a molten fluoride salt to form a eutectic mixture th...
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