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科研机构
西安交通大学 [398]
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期刊论文 [254]
会议论文 [144]
发表日期
2019 [13]
2018 [52]
2017 [50]
2016 [36]
2015 [38]
2014 [44]
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专题:西安交通大学
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Application of the Improved Spacer Grid Model in Subchannel Analysis Code
期刊论文
Nuclear Technology, 2019, 卷号: 205, 页码: 352-363
作者:
Dong, Siying
;
Liu, Wei
;
Liu, Yang
;
Shan, Jianqiang
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  |  
浏览/下载:10/0
  |  
提交时间:2019/11/19
Distributed resistance
Mixing vane
Spacer grid
Subchannel analysis
Turbulent mixing
Warm-Dense-Matter State of Iron Generated by Intense Heavy-Ion Beams
期刊论文
IEEE Transactions on Plasma Science, 2019, 卷号: 47, 页码: 853-857
作者:
Zhang, Lin
;
Zhao, Yongtao
;
Ren, Jieru
;
Li, Jianxing
;
Liu, Wei
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  |  
浏览/下载:49/0
  |  
提交时间:2019/11/19
Code simulation
Equation of state
Facility for antiproton and ion research
High intensity accelerator
Hydrodynamic behavior
Intense heavy ion beams
Planetary science
Warm dense matters
Secure Communications in Cooperative D2D Networks by Jointing Wyner's Code and Network Coding
期刊论文
IEEE ACCESS, 2019, 卷号: 7, 页码: 34533-34540
作者:
He, Hongliang
;
Ren, Pinyi
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  |  
浏览/下载:18/0
  |  
提交时间:2019/11/19
cooperative communications
physical-layer security
D2D
Sensitivity analysis and similarity evaluation of sodium-cooled fast reactor in large size
期刊论文
Annals of Nuclear Energy, 2019, 卷号: 125, 页码: 283-290
作者:
Zheng, Youqi
;
Qiao, Liang
;
Wan, Chenghui
;
Cao, Liangzhi
;
Liu, Yong
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  |  
浏览/下载:13/0
  |  
提交时间:2019/11/19
Code validation
Mixed oxide
Similarity analysis
Similarity evaluation
The Impact of Mixing Vane Arrangement on Mixing Coefficient ? for Subchannel Analysis
期刊论文
Nuclear Technology, 2019, 卷号: 205, 页码: 328-337
作者:
Wei, Cen
;
Yang, Bao-Wen
;
Han, Bin
;
Liu, Aiguo
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  |  
浏览/下载:9/0
  |  
提交时间:2019/11/19
CFD computation
Heat Transfer enhancement
Mixing coefficient
Mixing vane
Subchannel analysis
Subchannel code
Thermal non-uniformity
Turbulent mixing
Validation of SARAX for the China Fast Reactor with the extrapolated experimental data
期刊论文
Annals of Nuclear Energy, 2019, 卷号: 127, 页码: 188-195
作者:
Wan, Chenghui
;
Qiao, Liang
;
Zheng, Youqi
;
Cao, Liangzhi
;
Wu, Hongchun
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  |  
浏览/下载:34/0
  |  
提交时间:2019/11/19
Code validation
Nuclear data
Numerical results
Reference values
Relative uncertainty
Sensitivity/uncertainty analysis
Similarity analysis
Theoretical approach
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
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  |  
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
Comparison of the Subchannel Code CTF to Steady-State and Transient Heat Transfer Experiments at Intermediate Pressures in Water
期刊论文
Nuclear Technology, 2019, 卷号: 205, 页码: 364-376
作者:
Wu, Pan
;
Novog, David
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  |  
浏览/下载:16/0
  |  
提交时间:2019/11/19
Dry-out
Intermediate pressures
Onset of nucleate boiling
Steady state and transients
Subchannel code
Thermal-hydraulic codes
Transient experiments
Two-phase heat transfer
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
Development and verification of a model for generation of MSFR few-group homogenized cross-sections based on a Monte Carlo code OpenMC
期刊论文
Annals of Nuclear Energy, 2019, 卷号: 124, 页码: 187-197
作者:
Zhuang, Kun
;
Tang, Xiaobin
;
Cao, Liangzhi
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  |  
浏览/下载:5/0
  |  
提交时间:2019/11/19
Deterministic methods
Group parameters
MSFR
Neutronics
Neutronics parameters
OpenMC
Thermal neutron scattering
Two dimensions (2D)
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