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科研机构
西安交通大学 [93]
内容类型
期刊论文 [71]
会议论文 [22]
发表日期
2018 [11]
2017 [13]
2016 [5]
2015 [4]
2014 [13]
2013 [11]
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Study on Optimization Method for Periodical Tests of CPR1000 Nuclear Power Unit
期刊论文
Hedongli Gongcheng/Nuclear Power Engineering, 2018, 卷号: 39, 页码: 123-127
作者:
Yang, Bo
;
Zhang, Zhao
;
Zhao, Fuyu
;
Shen, Rongfa
收藏
  |  
浏览/下载:11/0
  |  
提交时间:2019/11/19
Nuclear power unit
Nuclear safety
Optimization method
Optimization scheme
Periodic tests
Reactor coolant systems
Residual heat removal systems
Safety analysis
Investigation on Nonuniformity of Heat Transfer in Triangular Subchannels of Supercritical Water Cooled Reactor
期刊论文
Hedongli Gongcheng/Nuclear Power Engineering, 2018, 卷号: 39, 页码: 33-39
作者:
Wang, Weishu
;
Hou, Yanliang
;
Xu, Weihui
;
Zhu, Xiaojing
;
Bi, Qincheng
收藏
  |  
浏览/下载:7/0
  |  
提交时间:2019/11/19
Circumferential angles
Heat transfer characteristics
Local heat transfer coefficient
Nonuniformity
Pitch-to-diameter ratios
SCWR
Subchannels
Supercritical water cooled reactors
Transient Simulations of CPR1000 Nuclear Power Plant Implementing Advanced Mechanical Shim Control System
期刊论文
Nuclear Science and Engineering, 2018
作者:
Wu, Shifa
;
Wan, Jiashuang
;
Song, Hongbing
;
Wei, Xinyu
;
Zhao, Fuyu
收藏
  |  
浏览/下载:4/0
  |  
提交时间:2019/11/19
Control performance
CPR1000
Full-scope simulation
Operational transients
Protection systems
Reactor control
Transient simulation
U-tube steam generators
Numerical Studies on Flow and Heat Transfer Characteristics of Fluoride Salt Cooled Pebble Bed Test Reactor
期刊论文
Hedongli Gongcheng/Nuclear Power Engineering, 2018, 卷号: 39, 页码: 001-005
作者:
Wei, Shiying
;
Wang, Chenglong
;
Tian, Wenxi
;
Su, Guanghui
;
Qiu, Suizheng
收藏
  |  
浏览/下载:14/0
  |  
提交时间:2019/11/26
Fluoride-salt-cooled high-temperature reactors (FHR)
Fuel pebbles
In-house codes
Maximum relative errors
Mechanism research
Test reactor
Thermal hydraulics
Velocity field
Development of Analysis Code for Pb-Bi Cooled Direct-Contact-Boiling Water Fast Reactor System
期刊论文
Hedongli Gongcheng/Nuclear Power Engineering, 2018, 卷号: 39, 页码: 067-070
作者:
Wei, Shiying
;
Wang, Chenglong
;
Su, Guanghui
;
Tian, Wenxi
;
Qiu, Suizheng
收藏
  |  
浏览/下载:14/0
  |  
提交时间:2019/11/26
Cladding failures
Coolant systems
Direct contact boiling
Lead-bismuth reactors
Reactor systems
Steady state and transients
System safety
Thermal hydraulics
Investigation of Flow and Heat Transfer for CAP1000 Reactor Internals with Direct Safety Injection
期刊论文
Hedongli Gongcheng/Nuclear Power Engineering, 2018, 卷号: 39, 页码: 016-021
作者:
Weng, Yu
;
Wang, Haijun
;
Wang, Haitao
;
Zhang, Ming
;
Feng, Shaodong
收藏
  |  
浏览/下载:5/0
  |  
提交时间:2019/11/26
Dimensionless correlation
Flow and heat transfer
Injection conditions
Radiation surveillance
Reactor internals
Safety injection
Surface heat transfer
Wall surface temperature
Development and Verification of a Transient Analysis Tool for Reactor System Using Supercritical CO2 Brayton Cycle as Power Conversion System
期刊论文
SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2018
作者:
Wu, Pan
;
Gao, Chuntian
;
Shan, Jianqiang
收藏
  |  
浏览/下载:8/0
  |  
提交时间:2019/11/26
Reactor Core Design of Micro Nuclear Power Source Applied for Underwater Vehicle
期刊论文
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2018, 卷号: 52, 页码: 646-651
作者:
Sun, Hao
;
Wang, Chenglong
;
Liu, Xiao
;
Tian, Wenxi
;
Qiu, Suizheng
收藏
  |  
浏览/下载:10/0
  |  
提交时间:2019/11/26
Design and application
MCNP
Monte Carlo programs
Nuclear power sources
ORIGEN
Power distributions
Reactor core designs
Underwater vehicles
Flow characteristic of single-phase natural circulation under ocean motions
期刊论文
Journal of Nuclear Science and Technology, 2018, 卷号: 55, 页码: 1366-1380
作者:
Wang, Sipeng
;
Yang, Bao-Wen
;
Zhou, Zhaobo
收藏
  |  
浏览/下载:17/0
  |  
提交时间:2019/11/26
Coupled motions
Floating nuclear power
Flow charac-teristics
Natural circulation
Natural circulation system
Nuclear reactor systems
Passive safety systems
Superposition effect
Conceptual design and analysis of a multipurpose micro nuclear reactor power source
期刊论文
ANNALS OF NUCLEAR ENERGY, 2018, 卷号: 121, 页码: 118-127
作者:
Sun, Hao
;
Wang, Chenglong
;
Ma, Pan
;
Liu, Xiao
;
Tian, Wenxi
收藏
  |  
浏览/下载:2/0
  |  
提交时间:2019/11/26
Heat pipe cooled reactor
Micro nuclear power source
Neutronics design and analysis
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