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科研机构
西安交通大学 [12]
合肥物质科学研究院 [3]
上海应用物理研究所 [1]
内容类型
期刊论文 [9]
会议论文 [7]
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2020 [2]
2018 [1]
2017 [3]
2016 [2]
2015 [5]
2014 [1]
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Development and testing of a coupled SuperMC and SUBCHANFLOW code for LWR simulations
期刊论文
ANNALS OF NUCLEAR ENERGY, 2020, 卷号: 144
作者:
Yu, Louhanrong
;
Wang, Lei
;
Liu, Chao
;
Wu, Bin
;
Song, Jing
收藏
  |  
浏览/下载:10/0
  |  
提交时间:2020/11/26
SuperMC
SUBCHANFLOW
Neutronics
Thermal-hydraulics
Coupling simulation
Core and blanket thermal-hydraulic analysis of a molten salt fast reactor based on coupling of OpenMC and OpenFOAM
期刊论文
NUCLEAR SCIENCE AND TECHNIQUES, 2020, 卷号: 31, 期号: 9, 页码: -
作者:
Deng, B
;
Cui, Y
;
Chen, JG
;
He, L
;
Xia, SP
收藏
  |  
浏览/下载:21/0
  |  
提交时间:2021/09/06
ENRICHMENT
DESIGN
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
Comparison of the subchannel code CTF to steady-state and transient heat transfer experiments at intermediate pressures in water
会议论文
作者:
Wu, Pan
;
Novog, David
收藏
  |  
浏览/下载:8/0
  |  
提交时间:2019/11/26
Dry-out
Intermediate pressures
Onset of nucleate boiling
Pressure transient
Steady state and transients
Thermal-hydraulic codes
Transient experiments
Two-phase heat transfer
Internal coupling of neutronics code NECP-X and sub-channel code SUBSC
会议论文
作者:
Chen, Jun
;
Cao, Liangzhi
;
Liu, Zhouyu
;
Wu, Hongchun
收藏
  |  
浏览/下载:5/0
  |  
提交时间:2019/11/26
Bench-mark problems
Coolant temperature
Internal coupling
NECP-X
Neutronics codes
Radial power distributions
SUBSC
Thermal hydraulics
A simulation of I2S-LWR selected transients
期刊论文
Annals of Nuclear Energy, 2017
作者:
Ward, Andrew M.
;
Wang, Mingjun
;
Neumann, Matthew D.
;
Memmott, Matthew
;
Manera, Annalisa
收藏
  |  
浏览/下载:9/0
  |  
提交时间:2019/11/26
Cladding temperatures
Departure from nucleate boiling ratios
Design basis accidents
Inherent safety
Innovative approaches
Integral configuration
Safety analysis
Thermal hydraulics codes
CLEAR-S: an integrated non-nuclear test facility for China lead-based research reactor
期刊论文
INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2016, 卷号: 40, 期号: 14, 页码: 1951-1956
作者:
Wu, Y.
收藏
  |  
浏览/下载:22/0
  |  
提交时间:2017/12/18
Liquid Lead-alloy
China Lead-based Research Reactor
Integrated Non-nuclear Test Facility
Clear-s
Neutronics and thermal-hydraulics coupling analysis of molten salt reactor at steady state
期刊论文
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2016, 卷号: 50, 期号: [db:dc_citation_issue], 页码: 1823-1827
作者:
Hu, Tian-Liang
;
Wu, Hong-Chun
;
Cao, Liang-Zhi
;
Zheng, You-Qi
;
Zhuang, Kun
收藏
  |  
浏览/下载:2/0
  |  
提交时间:2019/12/02
Analytic basis functions
Coupling analysis
Graphite-moderated
Power distributions
Steady-state analysis
Thermal hydraulics
Thermal hydraulics codes
Triangular geometry
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
Preliminary design of the I2S-LWR containment system
会议论文
作者:
Wang, Mingjun
;
Manera, Annalisa
;
Memmott, Matthew J.
;
Lee, John C.
;
Qiu, Suizheng
收藏
  |  
浏览/下载:5/0
  |  
提交时间:2019/12/02
Automatic depressurization systems
Containment
Integral reactors
Passive containment cooling systems
Passive cooling
Reactor Pressure Vessel
SBLOCA
Thermal-hydraulic codes
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