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科研机构
西安交通大学 [8]
清华大学 [4]
合肥物质科学研究院 [4]
华南理工大学 [1]
工程热物理研究所 [1]
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期刊论文 [14]
会议论文 [4]
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2019 [1]
2018 [1]
2017 [1]
2016 [3]
2015 [5]
2013 [1]
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Analysis of core blockage scenarios during pump shutdown accidents for small size lead-cooled fast reactor using RELAP5-HD
期刊论文
PROGRESS IN NUCLEAR ENERGY, 2019, 卷号: 111, 期号: 无, 页码: 205-210
作者:
Zou, Xiaoliang
;
Zhou, Tao
;
Zhang, Guangyu
;
Jin, Ming
;
Bai, Yunqing
收藏
  |  
浏览/下载:62/0
  |  
提交时间:2020/03/31
RELAP5-HD
LFR
Pump shutdown accidents
Reactor safety
Steady State and Transient Analysis of Novel Design Helium Cooled Ceramic Blanket (HCCB) System of China Fusion Engineering Test Reactor (CFETR)
期刊论文
JOURNAL OF FUSION ENERGY, 2018, 卷号: 37, 期号: 6, 页码: 308-316
作者:
Khan, Salah Ud-Din
;
Wang, Jian
;
Song, Yuntao
;
Khan, Shahab Ud-Din
;
Rana, Usman Ali
收藏
  |  
浏览/下载:41/0
  |  
提交时间:2019/12/25
Safety studies
Modified design of HCCB
Inbox LOCA
In-vessel LOCA
Parametric analysis
Authentication of design and safety
Thermal hydraulic responses of the Primary Heat Transfer System of the WCCB blanket to accident cases for CFETR
期刊论文
FUSION ENGINEERING AND DESIGN, 2017, 卷号: 121, 页码: 50-59
作者:
Cheng, Xiaoman
;
Huang, Kai
;
Liu, Songlin
;
Neilson, George H.
;
Khodak, Andrei
收藏
  |  
浏览/下载:30/0
  |  
提交时间:2018/08/16
Cfetr Primary Heat Transfer System
Wccb
Thermo-hydraulic
Accidents
Safety analysis of accident-tolerant fuel during LBLOCA
期刊论文
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2016, 卷号: 50, 期号: [db:dc_citation_issue], 页码: 1065-1071
作者:
Wu, Xiao-Li
;
Wang, Yang
;
Zhang, Ya-Pei
;
Tian, Wen-Xi
;
Su, Guang-Hui
收藏
  |  
浏览/下载:4/0
  |  
提交时间:2019/12/02
Accident tolerant fuels
Emergency Core Cooling System
Large break loss of coolant accidents
Mitigation measures
Peak cladding temperature
Preliminary assessment
Safety analysis
Severe accident
Uncertainty evaluation and application on important models during LBLOCA
期刊论文
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2016, 卷号: 50, 页码: 92-97
作者:
Yu, Ai-Min
;
Gou, Jun-Li
;
Ding, Wen-Jie
;
Shan, Jian-Qiang
;
Zhang, Bin
收藏
  |  
浏览/下载:6/0
  |  
提交时间:2019/11/26
Calculation results
Critical flow models
Large break loss of coolant accidents
Orthogonal series
Peak cladding temperature
Probability assessments
Uncertainty evaluation
Uncertainty range
Preliminary thermal hydraulic safety analysis of water-cooled ceramic breeder blanket for CFETR
期刊论文
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2016, 卷号: 53, 期号: 11, 页码: 1673-1680
作者:
Cheng, Xiaoman
;
Ma, Xuebin
;
Chen, Youhua
;
Huang, Kai
;
Liu, Songlin
收藏
  |  
浏览/下载:12/0
  |  
提交时间:2017/12/18
Cfetr
Blanket
Thermal Hydraulics
Accident Analysis
Relap5
Analysis of the SBLOCA on the improved CPR 1000 with passive systems
会议论文
作者:
Yang, Zijiang
;
Xiong, Xiaofei
;
Gou, Junli
;
Shan, Jianqiang
;
Zhang, Guomin
收藏
  |  
浏览/下载:3/0
  |  
提交时间:2019/12/02
Advanced nuclear power plants
CPR1000
In-containment refueling water storage tank
Passive systems
Passive technologies
RELAP5/MOD3.3
SBLOCA
Small break loss of coolant accidents
Simulations of ECC safety injection for single phase and stratified phase flow
会议论文
作者:
Qiu, Suizheng
;
Tian, Wenxi
;
Su, G. H.
;
Chen, Ronghua
收藏
  |  
浏览/下载:2/0
  |  
提交时间:2019/12/02
Direct contact condensation
High-temperature water
Pressurized thermal shock
Reactor Pressure Vessel
Small break loss of coolant accidents
Stratified flows
Temperature profiles
Thermal mixing
Experimental investigation of CCFL in pressurizer surge line with air-water
会议论文
作者:
Wang, Z. W.
;
Tian, W. X.
;
Yu, J. T.
;
Zhang, D. L.
;
Su, G. H.
收藏
  |  
浏览/下载:5/0
  |  
提交时间:2019/12/02
Automatic depressurization systems
CCFL
Counter-current flow limitation
Experimental investigations
Reactor Pressure Vessel
Small break loss of coolant accidents
Surge lines
Visualization experiment
Severe accident analysis of a PWR spent fuel pool in case of loss of pool coolant
会议论文
作者:
Wu, Xiaoli
;
Zhang, Yapei
;
Tian, Wenxi
;
Su, Guanghui
;
Qiu, Suizheng
收藏
  |  
浏览/下载:3/0
  |  
提交时间:2019/12/02
Accident scenarios
Fuel rod claddings
Hydrogen generations
MAAP5
Mitigation measures
Nuclear accidents
Radioactive fission products
Spent fuel pools
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