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清华大学 [9]
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期刊论文 [24]
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Neutronics and shielding design of CFETR HCCB blanket
期刊论文
FUSION ENGINEERING AND DESIGN, 2021, 卷号: 172
作者:
Cao, Qixiang
;
Wang, Xiaoyu
;
Wu, Xinghua
;
Yin, Miao
;
Qu, Shen
收藏
  |  
浏览/下载:24/0
  |  
提交时间:2022/01/10
CFETR
HCCB TBB
Neutronics design
TBR
Shielding design
Investigation on the Tritium Self-Sufficiency and Neutron Shielding Based on a Water-Cooled Blanket for CFETR at 1.5 GW
期刊论文
IEEE TRANSACTIONS ON PLASMA SCIENCE, 2021, 卷号: 49
作者:
Li, Jie
;
Zhang, Jie
;
Liu, Changle
;
Liu, Xiaogang
;
Gao, Xiang
收藏
  |  
浏览/下载:56/0
  |  
提交时间:2021/11/15
Neutrons
Plasmas
Solid modeling
Inductors
Production
Optimization
Loading
China Fusion Engineering Test Reactor (CFETR)
neutronics study
neutron wall loading (NWL)
tritium breeding ratio (TBR)
water-cooled ceramic breeder (WCCB)
Th-U Breeding Performances in an Optimized Molten Chloride Salt Fast Reactor
期刊论文
NUCLEAR SCIENCE AND ENGINEERING, 2021, 卷号: 195, 期号: 2, 页码: 185-202
作者:
He, LY
;
Xia, SP
;
Chen, JG
;
Liu, GM
;
Wu, JH
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  |  
浏览/下载:38/0
  |  
提交时间:2021/09/06
THORIUM FUEL-CYCLE
Numerical approach to study the thermal-hydraulic characteristics of Reactor Vessel Cooling system in sodium-cooled fast reactors
期刊论文
Progress in Nuclear Energy, 2019, 卷号: 110, 页码: 213-223
作者:
Song, Ping
;
Zhang, Dalin
;
Feng, Tangtao
;
Wang, Shibao
;
Chen, Jing
收藏
  |  
浏览/下载:32/0
  |  
提交时间:2019/11/19
Code development
Decay heat removal
Design and optimization
Fast breeder reactors
Numerical approaches
Reactor vessel cooling
Transient characteristic
Transient thermal-hydraulic
Numerical approach to study the thermal-hydraulic characteristics of Reactor Vessel Cooling system in sodium-cooled fast reactors
期刊论文
Progress in Nuclear Energy, 2019, 卷号: Vol.110, 页码: 213-223
作者:
Song, Ping
;
Zhang, Dalin
;
Feng, Tangtao
;
Wang, Shibao
;
Chen, Jing
收藏
  |  
浏览/下载:7/0
  |  
提交时间:2019/12/13
Code development
Decay heat removal
Design and optimization
Fast breeder reactors
Numerical approaches
Reactor vessel cooling
Transient characteristic
Transient thermal-hydraulic
Thermal hydraulic analysis of water cooled blanket under transient condition
期刊论文
FUSION ENGINEERING AND DESIGN, 2018, 卷号: 136, 页码: 151-156
作者:
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浏览/下载:32/0
  |  
提交时间:2019/12/25
Water cooled blanket
Safety analysis
Neutronic study of a combined fast fission FFHR and thermal fission FFHR system using thorium bearing molten salt fuel
期刊论文
ANNALS OF NUCLEAR ENERGY, 2018, 卷号: 112, 页码: 666-672
作者:
Xiao, S. C.
;
Zhao, J.
;
Zhou, Z.
;
Yang, Y.
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  |  
浏览/下载:18/0
  |  
提交时间:2018/05/31
Fast breeder
Thermal burner
U-233 breeding
Th-U cycle
Molten salt fuel
The feasibility research of thorium breeding using fluoride salt as a fast reactor coolant
期刊论文
PROGRESS IN NUCLEAR ENERGY, 2017, 卷号: 101, 期号: -, 页码: 199-208
作者:
Peng, Y
;
Zhu, GF
;
Zou, Y
;
Liu, YF
;
Yu, XH
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  |  
浏览/下载:11/0
  |  
提交时间:2018/08/30
Burn Reactors
Fuel-cycle
Sustainability
Perspectives
Neutronics Comparison Analysis of the Water Cooled Ceramics Breeding Blanket for CFETR
期刊论文
PLASMA SCIENCE & TECHNOLOGY, 2016, 卷号: 18, 期号: 2, 页码: 179-183
作者:
Li Jia
;
Zhang Xiaokang
;
Gao Fangfang
;
Pu Yong
收藏
  |  
浏览/下载:19/0
  |  
提交时间:2017/07/27
Cfetr
Blanket
Neutronics Modeling
Nuclear Performance
Neutronics studies on the feasibility of developing fast breeder reactor with flexible breeding ratio
期刊论文
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2016, 卷号: 53, 期号: [db:dc_citation_issue], 页码: 129-138
作者:
Xiao, Yunlong
;
Wu, Hongchun
;
Zheng, Youqi
;
Wang, Kunpeng
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  |  
浏览/下载:4/0
  |  
提交时间:2019/12/02
fast reactor
fuel breeding
flexible breeding ratio
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