搜索筛选:
搜索耗时1.3673秒,为你在为你在102,285,761篇论文里面共找到 12 篇相符的论文内容
发布年度:
Neutron excess method for performance assessment of thoriumbased fuel in a breed-and-burn reactor wi
[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
...
Preliminary analysis of fuel cycle performance for a small modular heavy water-moderated thorium mol
[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
...
,Influence of 235U enrichment on the moderator temperature coefficient of reactivity in a graphite-m
[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...
,Effects of fuel salt composition on fuel salt temperature coefficient (FSTC) for an under-moderated
[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)...
Core and blanket thermal–hydraulic analysis of a molten salt fast reactor based on coupling of OpenM
[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...
相关搜索：
