搜索筛选:
搜索耗时0.0952秒,为你在为你在102,285,761篇论文里面共找到 14 篇相符的论文内容
发布年度:
Application of Monte Carlo method to calculate the effective delayed neutron fraction in molten salt
[期刊论文] 作者：Gui-Feng Zhu,Rui Yan,Hong-Hua,
来源：核技术:英文版 年份：2019
Delayed neutron loss is an important parameter in the safety analysis of molten salt reactors. In this study, to obtain the effective delayed neutron fraction u...
Research on the effect of the heavy nuclei amount on the temperature reactivity coefficient in a sma
[期刊论文] 作者：Meng-Lu Tan,Gui-Feng Zhu,Yang,
来源：核技术:英文版 年份：2019
Small modular thorium-based graphite-moderated molten salt reactors (smTMSRs), which combine the advantages of small modular reactors and molten salt reactors,...
Neutronics physics analysis of a large fluoride-salt-cooled solidfuel fast reactor with Th-based fue
[期刊论文] 作者：Yu Peng,Gui-Feng Zhu,Yang Zou,,
来源：核技术：英文版 年份：2017
Fast reactors based on thorium fuel have enhanced inherent safety. Fluoride salt performs well as a coolant in high-temperature nuclear systems. In this paper,w...
[期刊论文] 作者：Rui-Min Ji,Ye Dai,Gui-Feng Zhu,
来源：核技术：英文版 年份：2017
The 10 MW_(th) solid-fueled thorium molten salt reactor(TMSR-SF1) is a FLi Be salt-cooled pebble bed reactor to be deployed in 5–10 years, designed by the TMSR...
Neutronics physics analysis of a large fluoride-salt-cooled solid-fuel fast reactor with Th-based fu
[期刊论文] 作者：Yu Peng,Gui-Feng Zhu,Yang Zou,Si-Jia Liu,Hong-Jie Xu,,
来源：Nuclear Science and Techniques 年份：2017
Fast reactors based on thorium fuel have enhanced inherent safety. Fluoride salt performs well as a coolant in high-temperature nuclear systems. In this paper,w...
,Neutronics physics analysis of a large fluoride-salt-cooled solid-fuel fast reactor with Th-based f
[期刊论文] 作者：Yu Peng,Gui-Feng Zhu,Yang Zou,Si-Jia Liu,Hong-Jie Xu,
来源：核技术（英文版） 年份：2017
Fast reactors based on thorium fuel have enhanced inherent safety.Fluoride salt performs well as a coolant in high-temperature nuclear systems.In this paper,we...
,Research on the effect of the heavy nuclei amount on the temperature reactivity coefficient in a sm
[期刊论文] 作者：Meng-Lu Tan,Gui-Feng Zhu,Yang Zou,Xiao-Han Yu,Ye Dai,
来源：核技术（英文版） 年份：2019
Small modular thorium-based graphite-moder-ated molten salt reactors (smTMSRs), which combine the advantages of small modular reactors and molten salt reactors,...
[期刊论文] 作者：Pu Yang,Zuo-Kang Lin,Wei-shi Wan,Gui-Feng Zhu,Xiao-Han Yu,Zhi-Min Dai,
来源：核技术（英文版） 年份：2020
Present designs for molten salt thermal reactors require complex online processing systems,which are technologically challenging,while an accelerator-driven sub...
[期刊论文] 作者：Rui-Min Ji,Ye Dai,Gui-Feng Zhu,Shi-He Yu,Yang Zou,Gui-Min Liu,,
来源：Nuclear Science and Techniques 年份：2017
The 10 MW_(th) solid-fueled thorium molten salt reactor(TMSR-SF1) is a FLi Be salt-cooled pebble bed reactor to be deployed in 5–10 years, designed by the TMSR...
[期刊论文] 作者：Liang Chen,Rui Yan,Xu-Zhong Kang,Gui-Feng Zhu,Bo Zhou,Liao-Yuan He,Yang Zou,Hong-Jie Xu,
来源：核技术（英文版） 年份：2021
The production of radionuclides 90Sr and 131I in molten salt reactors is an attractive option to address the global shortage of radionuclides. This study evalua...
,Application of Monte Carlo method to calculate the effective delayed neutron fraction in molten sal
[期刊论文] 作者：Gui-Feng Zhu,Rui Yan,Hong-Hua Peng,Rui-Min Ji,Shi-He Yu,Ya-Fen Liu,Jian Tian,Bo Xu,
来源：核技术（英文版） 年份：2019
Delayed neutron loss is an important parameter in the safety analysis of molten salt reactors.In this study,to obtain the effective delayed neutron fraction und...
[期刊论文] 作者：Meng-Lu Tan,Gui-Feng Zhu,Zheng-De Zhang,Yang Zou,Xiao-Han Yu,Cheng-Gang Yu,Ye Dai,Rui Yan,
来源：核技术（英文版） 年份：2022
The advantages of once-through molten salt reactors include readily available fuel,low nuclear prolif-eration risk,and low technical difficulty.It is potentially the most easily commercialized fuel cycle mode for molten salt reactors.Howeve......
[期刊论文] 作者：Bo Zhou,Xiao-Han Yu,Yang Zou,Pu Yang,Shi-He Yu,Ya-Fen Liu,Xu-Zhong Kang,Gui-Feng Zhu,Rui Yan,
来源：核技术（英文版） 年份：2020
In this study, a numerical flow model of the fission products (FPs) in the primary loop system of a molten salt reactor (MSR) was established and solved using M...
[期刊论文] 作者：Shi-He Yu,Ya-Fen Liu,Pu Yang,Rui-Min Ji,Gui-Feng Zhu,Bo Zhou,Xu-Zhong Kang,Rui Yan,Yang Zou,Ye Dai,
来源：核技术（英文版） 年份：2021
The neutronic properties of molten salt reactors (MSRs) differ from those of traditional solid fuel reactors owing to their nuclear fuel particularity. Based on...
相关搜索：
