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西安交通大学 [5]
清华大学 [3]
上海应用物理研究所 [2]
湖南大学 [1]
合肥物质科学研究院 [1]
近代物理研究所 [1]
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期刊论文 [13]
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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
收藏
  |  
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:31/0
  |  
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:
Cui, Qinglan
;
Guo, Yun
;
Peng, Changhong
;
Bao, Hui
收藏
  |  
浏览/下载:31/0
  |  
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.
收藏
  |  
浏览/下载:17/0
  |  
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
收藏
  |  
浏览/下载:11/0
  |  
提交时间:2018/08/30
Burn Reactors
Fuel-cycle
Sustainability
Perspectives
Preliminary study of transition scheme for flexible fast breeder reactor
期刊论文
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2015, 卷号: 49, 期号: [db:dc_citation_issue], 页码: 142-146
作者:
Xiao, Yun-Long
;
Wu, Hong-Chun
;
Zheng, You-Qi
;
Yuan, Xian-Bao
;
Wang, Kun-Peng
收藏
  |  
浏览/下载:6/0
  |  
提交时间:2019/12/02
Breeding ratio
Fast breeder reactors
Fuel design
Reactor designs
Requirement change
Scheme design
Numerical study of radial stepwise fuel load reshuffling traveling wave reactor
期刊论文
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2015, 卷号: 49, 期号: [db:dc_citation_issue], 页码: 694-699
作者:
Zhang, Da-Lin
;
Zheng, Mei-Yin
;
Tian, Wen-Xi
;
Qiu, Sui-Zheng
;
Su, Guang-Hui
收藏
  |  
浏览/下载:4/0
  |  
提交时间:2019/12/02
Asymptotic characteristics
Asymptotic steady state
Axial power distribution
Fast breeder reactors
Fuel loads
Numerical calculation
Realistic applications
Traveling wave
Economic evaluation of fast reactor fuel cycling
期刊论文
Hedongli Gongcheng/Nuclear Power Engineering, 2012, 卷号: 33, 期号: [db:dc_citation_issue], 页码: 134-137
作者:
Hu, Ping
;
Zhao, Fu-Yu
;
Yan, Zhou
;
Li, Chong
收藏
  |  
浏览/下载:4/0
  |  
提交时间:2019/12/10
Cycling process
Economic evaluations
Economy
Fast breeder reactors
Fast reactor fuel cycles
Natural uranium
Nuclear fuel cycles
Once-through fuel cycle
Subchannel model of analysis code ATHAS-LMR for LMFBR
期刊论文
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2012, 卷号: 46, 期号: [db:dc_citation_issue], 页码: 695-700
作者:
Chen, Xuan-Xiang
;
Wu, Pan
;
Shan, Jian-Qiang
收藏
  |  
浏览/下载:6/0
  |  
提交时间:2019/12/10
ATHAS-LMR code
Distributed resistance
Flow blockage
Liquid metal cooled fast breeder reactors
Model of analysis
Normal operations
Subchannels
Thermal-hydraulic performance
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