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科研机构
西安交通大学 [8]
上海应用物理研究所 [2]
内容类型
会议论文 [10]
发表日期
2017 [10]
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发表日期:2017
内容类型:会议论文
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Criticality safety analysis and shielding calculation of spent fuel transporatation cask
会议论文
作者:
Xu, Sihan
;
Du, Xin
;
Wang, Sheng
;
Hu, Haijun
;
Fan, Fei
收藏
  |  
浏览/下载:7/0
  |  
提交时间:2019/11/26
Accident conditions
Criticality calculations
Criticality safety
Radiation source
Regulatory requirements
Shielding analysis
Shielding calculation
Spent fuel assemblies
Review on thermal-hydraulic characterisics of nuclear reactors under ocean conditions
会议论文
作者:
Wang, Sipeng
;
Yang, Bao-Wen
;
Zhou, Zhaobo
;
Liu, Xirui
;
Long, Jianping
收藏
  |  
浏览/下载:8/0
  |  
提交时间:2019/11/26
Critical heat flux(CHF)
Floating nuclear power
Flow and heat transfer
High temperature high pressure
Ocean conditions
Thermal hydraulics
Three dimensional geometry
Two-phase flow instabilities
Numerical study on the effect of grid mixing span in 2×1 spacer grid
会议论文
作者:
Han, Bin
;
Yang, Bao-Wen
;
Zhou, Zhaobo
;
Zha, Yudong
收藏
  |  
浏览/下载:6/0
  |  
提交时间:2019/11/26
Computer fluid dynamics
Fuel assembly
Fundamental mechanisms
Grid span
Mixing characteristics
Mixing performance
Spacer grid
Thermal-hydraulic conditions
Heat loss simulations in large scale rod bundle tests
会议论文
作者:
Liu, Aiguo
;
Yang, Bao-Wen
;
Zha, Yudong
收藏
  |  
浏览/下载:6/0
  |  
提交时间:2019/11/26
Analytical method
Loss characteristics
Operating condition
Operation conditions
RELAP 5
Rod bundles
Steady-state condition
Temperature differences
IAEA's coordinated research project on EBR-II Shutdown heat removal tests
会议论文
作者:
Batra, Chirayu
;
Kriventsev, Vladimir
;
Monti, Stefano
;
Briggs, L.
;
Su, G.
收藏
  |  
浏览/下载:4/0
  |  
提交时间:2019/11/26
Argonne National Laboratory
Coordinated research projects
EBR-II
Heat removal
Initial and boundary conditions
International atomic energy agency
Passive safety
Reactor thermal hydraulics
The influence of guide tube diameters on flow field in rod bundles
会议论文
作者:
Mao, Hu
;
Yang, Bao-Wen
;
Liu, Xirui
收藏
  |  
浏览/下载:3/0
  |  
提交时间:2019/11/26
Adiabatic conditions
Cell grids
Coolant temperature
Heated conditions
Mixing efficiency
Subchannel analysis
Temperature differences
Thermal-hydraulic analysis
Influence study of actuation conditions of passive safety system on Sgtr
会议论文
作者:
Yang, Zijiang
;
Gou, Junli
;
Shan, Jianqiang
收藏
  |  
浏览/下载:5/0
  |  
提交时间:2019/11/26
Actuation conditions
Advanced nuclear power plants
CPR1000
In-containment refueling water storage tank
Modification
Passive safety systems
Passive technologies
Transient phenomenon
Review of CHF Mechanisms models
会议论文
作者:
Yang, Bao-Wen
;
Liu, Xirui
;
Mao, Hu
收藏
  |  
浏览/下载:4/0
  |  
提交时间:2019/11/26
Boiling heat transfer
Critical heat flux(CHF)
Empirical correlations
Heat transfer mechanism
Local conditions
Non-local conditions
Temperature-controlled system
Thermal-hydraulic conditions
BREEDING PROPERTIES STUDY ON HIGH POWER THORIUM MOLTEN SALT REACTOR
会议论文
Shanghai, PEOPLES R CHINA, JUL 02-06, 2017
作者:
Liu, YF
;
Guo, R
;
Cai, XZ
;
Yan, R
;
Zou, Y
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  |  
浏览/下载:7/0
  |  
提交时间:2019/12/31
THERMAL HYDRAULICS ANALYSIS OF THE FLUORIDE-SALT-COOLED, HIGH TEMPERATURE REACTOR
会议论文
Shanghai, PEOPLES R CHINA, JUL 02-06, 2017
作者:
Fu, Y
;
Sun, Q
;
Zhou, C
;
Zou, Y
收藏
  |  
浏览/下载:12/0
  |  
提交时间:2019/12/31
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