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西安交通大学 [15]
合肥物质科学研究院 [3]
力学研究所 [2]
清华大学 [2]
上海应用物理研究所 [1]
武汉岩土力学研究所 [1]
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期刊论文 [18]
会议论文 [6]
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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
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  |  
浏览/下载:20/0
  |  
提交时间:2021/09/06
ENRICHMENT
DESIGN
Modelling of reactor pressure vessel subjected to pressurized thermal shock using 3D-XFEM
期刊论文
NUCLEAR ENGINEERING AND DESIGN, 2019, 卷号: 353, 页码: 13
作者:
Niceno B
;
Jaros M
;
Qian GA(钱桂安)
;
Niffenegger M
;
Mora DF
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  |  
浏览/下载:68/0
  |  
提交时间:2019/11/26
Pressurized thermal shock
Large Break LOCA
Stress intensity factor
Reactor pressure vessel
Fracture mechanics
XFEM
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
Thermal-hydraulic analysis code development for sodium heated once-through steam generator
期刊论文
Annals of Nuclear Energy, 2019, 卷号: 127, 页码: 385-394
作者:
Xu, Rongshuan
;
Zhang, Dalin
;
Tian, Wenxi
;
Qiu, Suizheng
;
Su, G.H.
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  |  
浏览/下载:11/0
  |  
提交时间:2019/11/19
China experiment fast reactor
Computer codes
Generate electricity
Once through steam generator
Sodium cooled fast reactors (SFR)
Thermal hydraulic modeling
Thermal hydraulic parameters
Thermal-hydraulic analysis
Uncertainties in pressurized thermal shock analyses
会议论文
San Antonio, TX, United states, July 14, 2019 - July 19, 2019
作者:
Niffenegger M
;
Garrido OC
;
Mora DF
;
Qian GA(钱桂安)
;
Mukin R
收藏
  |  
浏览/下载:15/0
  |  
提交时间:2020/11/20
Computational fluid dynamics
Finite element method
Pressurized thermal shock
Probabilistic fracture mechanics
Warm pre-stressing
Design, Analysis, and Optimization of the Cryopanel Cooling System for CFETR Torus Cryopump
期刊论文
IEEE TRANSACTIONS ON PLASMA SCIENCE, 2018, 卷号: 46, 期号: 5, 页码: 1653-1657
作者:
Chen, Changqi
;
Chen, Chen
;
Wang, Guodong
;
Wang, Qingsheng
;
Yao, Damao
收藏
  |  
浏览/下载:24/0
  |  
提交时间:2019/08/23
Cryopanel cooling system
stress distribution
temperature distribution
thermal-hydraulic calculation
Transient thermal-hydraulic evaluation of lead-bismuth fast reactor by coupling sub-channel and system analysis codes
期刊论文
NUCLEAR ENGINEERING AND DESIGN, 2018, 卷号: 337, 页码: 228-235
作者:
Wei, Shiying
;
Wang, Chenglong
;
Tian, Wenxi
;
Qiu, Suizheng
;
Su, G. H.
收藏
  |  
浏览/下载:4/0
  |  
提交时间:2019/11/26
Coupling thermal-hydraulic analysis
Lead-based fast reactor
System safety analysis
Sub-channel analysis
Preliminary design of the I2S-LWR containment system
期刊论文
Annals of Nuclear Energy, 2018
作者:
Wang, Mingjun
;
Manera, Annalisa
;
Memmott, Matthew J
;
Lee, John C.
;
Tian, Wenxi
收藏
  |  
浏览/下载:2/0
  |  
提交时间:2019/11/26
Automatic depressurization systems
Containment
Integral reactors
Passive containment cooling systems
Passive cooling
Reactor Pressure Vessel
SBLOCA
Thermal-hydraulic codes
Comparative modelling of the coupled thermal-hydraulic-mechanical (THM) processes in a heated bentonite pellet column with hydration
期刊论文
ENVIRONMENTAL EARTH SCIENCES, 2018, 卷号: 77, 期号: 3, 页码: -
作者:
Shao, H.
;
Graupner, B. J.
;
Wang, X. R.
;
Nguyen, T. S.
;
Li, Z.
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  |  
浏览/下载:30/0
  |  
提交时间:2018/06/05
Mont Terri
Clay rock
Bentonite
Heater experiment
Coupled THM processes
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