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西安交通大学 [154]
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期刊论文 [150]
会议论文 [4]
发表日期
2019 [5]
2018 [22]
2017 [18]
2016 [17]
2015 [27]
2014 [21]
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专题:西安交通大学
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Spatial temperature distribution of fuel assembly pre-simulation for a new simple core degradation experiment
期刊论文
Progress in Nuclear Energy, 2019, 卷号: 111, 页码: 174-182
作者:
Feng, Tangtao
;
Tian, Wenxi
;
Song, Ping
;
Wang, Jun
;
Wang, Mingjun
收藏
  |  
浏览/下载:114/0
  |  
提交时间:2019/11/19
CORA
Experiment condition
International standards
MELCOR
Mitigation measures
Numerical analysis models
Peak temperatures
Spatial temperature distribution
Transient thermal-hydraulic analysis of thermionic space reactor TOPAZ-II with modified RELAP5
期刊论文
Progress in Nuclear Energy, 2019, 卷号: 112, 页码: 209-224
作者:
Tang, Simiao
;
Sun, Hao
;
Wang, Chenglong
;
Tian, Wenxi
;
Qiu, Suizheng
收藏
  |  
浏览/下载:14/0
  |  
提交时间:2019/11/19
Heat transfer correlation
Reactivity insertion
RELAP5 modification
Space nuclear reactors
Steady-state condition
Thermal-hydraulic analysis
Thermionic fuel elements
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: 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
Development and verification of resonance elastic scattering kernel processing module in nuclear data processing code NECP-Atlas
期刊论文
Progress in Nuclear Energy, 2019, 卷号: 110, 页码: 301-310
作者:
Xu, Jialong
;
Zu, Tiejun
;
Cao, Liangzhi
收藏
  |  
浏览/下载:123/0
  |  
提交时间:2019/11/19
Anisotropic scattering
Fuel temperature
NECP-Atlas
Neutron energy spectrum
Resonance elastic scattering
Scattering effects
Scattering kernels
Scattering matrices
Three-dimensional study on the hydraulic characteristics under the steam generator (SG) tube plugging operations for AP1000
期刊论文
Progress in Nuclear Energy, 2019, 卷号: 112, 页码: 63-74
作者:
Zhao, Xiaohan
;
Wang, Mingjun
;
Chen, Chong
;
Wang, Xi
;
Ju, Haoran
收藏
  |  
浏览/下载:12/0
  |  
提交时间:2019/11/19
AP1000
Hydraulic characteristic
Hydraulic performance
Maintenance strategies
Porous media methods
Porous medium
Radiation environments
Thermal-hydraulic simulations
Preliminary verification of a transient analysis code TSACO for helium cooled system
期刊论文
PROGRESS IN NUCLEAR ENERGY, 2018, 卷号: 104, 页码: 60-66
作者:
Wang, Jie
;
Su, G. H.
;
Lu, Wei
;
Liu, Dong
收藏
  |  
浏览/下载:6/0
  |  
提交时间:2019/11/19
Code verification
Uncertainty analysis
HE-FUS3 facility
TSACO
Transient safety analysis for simplified accelerator driven system with gas-lift pump
期刊论文
PROGRESS IN NUCLEAR ENERGY, 2018, 卷号: 106, 页码: 181-194
作者:
Zuo, Juanli
;
Tian, Wenxi
;
Qiu, Suizheng
;
Su, Guanghui
收藏
  |  
浏览/下载:3/0
  |  
提交时间:2019/11/19
Accelerator driven system
Gas-lift pump
TASAR code
Transient safety analysis
Conceptual design and comprehensive optimization analysis of a fusion-fission hybrid reactor water-cooled pressure tube blanket
会议论文
作者:
Cui, Shijie
;
Zhang, Dalin
;
Gao, Xinli
;
Tian, Wenxi
;
Su, G. H.
收藏
  |  
浏览/下载:6/0
  |  
提交时间:2019/11/26
Water-cooled pressure tube blanket
Thermal-mechanical coupling
First wall
Conceptual design
Fusion-fission hybrid reactor
ApproxFTL: On the Performance and Lifetime Improvement of 3-D NAND Flash-Based SSDs
期刊论文
IEEE TRANSACTIONS ON COMPUTER-AIDED DESIGN OF INTEGRATED CIRCUITS AND SYSTEMS, 2018, 卷号: 37, 页码: 1957-1970
作者:
Cui, Jinhua
;
Zhang, Youtao
;
Shi, Liang
;
Xue, Chun Jason
;
Wu, Weiguo
收藏
  |  
浏览/下载:4/0
  |  
提交时间:2019/11/26
approximate storage
3-D flash memory
reliability
The development and validation of the inter-wrapper flow model in sodium-cooled fast reactors
期刊论文
PROGRESS IN NUCLEAR ENERGY, 2018, 卷号: 108, 页码: 54-65
作者:
Yue, Nina
;
Zhang, Dalin
收藏
  |  
浏览/下载:7/0
  |  
提交时间:2019/11/26
Sodium-cooled fast reactor
Code development
Sensitivity analyses
Inter-wrapper flow
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