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科研机构
西安交通大学 [32]
内容类型
期刊论文 [22]
会议论文 [10]
发表日期
2018 [4]
2017 [4]
2016 [1]
2015 [3]
2014 [2]
2013 [8]
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专题:西安交通大学
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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
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
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
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
ALISA project: Large-scale experimental facilities for severe accidents studies in Europe and in China
会议论文
作者:
Miassoedov, A.
;
Liao, Y.
;
Gaus-Liu, X.
;
Journeau, C.
;
Cassiaut-Louis, N.
收藏
  |  
浏览/下载:11/0
  |  
提交时间:2019/11/26
Experimental activities
Experimental facilities
Experimental platform
Large scale experiments
Large-scale research
Reactor Pressure Vessel
Research organization
Severe accident management
Investigation of transient flow and heat transfer for passive nuclear reactor direct safety injection
会议论文
作者:
Weng, Yu
;
Liu, Lang
;
Jiang, Yang
;
Gu, Hongfang
;
Wang, Haijun
收藏
  |  
浏览/下载:2/0
  |  
提交时间:2019/11/26
Computational fluid dynamics methods
Correlation degree
Direct vessel injection systems
Heat distribution
Radiation surveillance
Reactor internals
Reactor Pressure Vessel
Reactor safety analysis
Research on reactor safety analysis method due to thermal system change of secondary circuit
期刊论文
Hedongli Gongcheng/Nuclear Power Engineering, 2017, 卷号: 38, 页码: 46-50
作者:
Zhang, Zhao
;
Tang, Qi
;
Wei, Yanhui
;
Shen, Rongfa
;
Sheng, Guolong
收藏
  |  
浏览/下载:15/0
  |  
提交时间:2019/11/26
Full scope simulators
High pressure
M310
Reactor safety analysis
Secondary circuit
Thermal economy
Thermal systems
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
Uncertainty analysis of transportable fluoride-salt-cooled high temperature reactor (TFHR) using dakota coupled with relap5-3D
会议论文
作者:
Wang, Chenglong
;
Sun, Kaichao
;
Hu, Lin-Wen
;
Qiu, Suizheng
;
Su, Guanghui
收藏
  |  
浏览/下载:3/0
  |  
提交时间:2019/11/26
Best estimates
Confidence levels
Design optimization
Fuel temperature
Reactor safety
Steady state calculations
Systematic uncertainties
Thermal hydraulics
Development and verification of system safety analysis code TSACO
期刊论文
Hedongli Gongcheng/Nuclear Power Engineering, 2015, 卷号: 36, 期号: [db:dc_citation_issue], 页码: 4-8
作者:
Wang, Jie
;
Pan, Junjie
;
Feng, Jintao
;
Su, Guanghui
收藏
  |  
浏览/下载:8/0
  |  
提交时间:2019/12/02
Code verification
Computational results
Dynamic behaviors
Measured temperatures
Outlet temperature
Safety analysis codes
System safety
Thermal hydraulics
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