兰州大学机构库

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Transient analysis of the CiADS reactor core loaded with nitride fuel 期刊论文
ANNALS OF NUCLEAR ENERGY, 2023, 卷号: 182
Authors:  Liu, Bo;  Li, Song;  Zhang, You-Peng;  Wallenius, Janne;  Xi, Bin;  Gu, Long;  Li, Jin-Yang;  Wang, Di-Si;  Jiang, Wei;  Zhang, Lu...Liu, Bo;  Li, Song;  Zhang, You-Peng;  Wallenius, Janne;  Xi, Bin;  Gu, Long;  Li, Jin-Yang;  Wang, Di-Si;  Jiang, Wei;  Zhang, Lu
Favorite  |    Submit date:2023/11/28
CiADS  SAS4A  SASSYS-1  Transient analysis  Nitride fuel  
Analysis of the stress field in the reactor vessel of the China Initiative Accelerator Driven System during postulated ULOF and UTOP transients 期刊论文
ANNALS OF NUCLEAR ENERGY, 2023, 卷号: 194
Authors:  Huang, Zi-Nan;  Li, Yun-Xiang;  Li, Song;  Xi, Bin;  Zhang, You-Peng;  Meng, Lu;  Wanga, Di-Si;  Liu, Bo;  Gu, Long;  Peng, Tian-Ji...Huang, Zi-Nan;  Li, Yun-Xiang;  Li, Song;  Xi, Bin;  Zhang, You-Peng;  Meng, Lu;  Wanga, Di-Si;  Liu, Bo;  Gu, Long;  Peng, Tian-Ji;  Zhang, Lu;  Jiang, Wei;  Wallenius, Janne
Favorite  |    Submit date:2023/11/28
Finite element analysis  CiADS  Reactor vessel  ADINA  Stress  
Analysis of the Accelerator-Driven System Fuel Assembly during the Steam Generator Tube Rupture Accident 期刊论文
MATERIALS, 2021, 卷号: 14, 期号: 8
Authors:  Wang, Di-Si;  Liu, Bo;  Yang, Sheng;  Xi, Bin;  Gu, Long;  Li, Jin-Yang;  Wallenius, Janne;  Zhang, You-Peng
Adobe PDF(10265Kb)  |  Favorite  |    Submit date:2021/06/17
accelerator-driven systemheavy liquid metalCFD simulationtwo-phase flow  Accelerator driven system  Calculation software  Computational fluid dynamics simulations  Coolant temperature distribution  Heating conditions  Maximum temperature  Steam generator tube ruptures  VOF (volume of fluid)  
Axial expansion for prompt safety of a small lead-cooled reactor 期刊论文
ANNALS OF NUCLEAR ENERGY, 2020, 卷号: 147
Authors:  Zhang, You-Peng;  Wallenius, Janne;  Gu, Long;  Yang, Sheng;  Zhao, Yi-Yang;  Li, Jin-Yang;  Peng, Tian-Ji
Favorite  |    Submit date:2020/12/18
Lead-cooled fast reactor  SAS4A/SASSYS-1 code  Transient analysis  Minor actinide transmutation  
Transient analyses for China initiative Accelerator Driven System using the extended BELLA code 期刊论文
ANNALS OF NUCLEAR ENERGY, 2023, 卷号: 190
Authors:  Wang, Guan;  Wallenius, Janne;  Yu, Rui;  Jiang, Wei;  Zhang, Lu;  Sheng, Xin;  Yun, Di;  Gu, Long
Favorite  |    Submit date:2023/07/18
CiADS  Subcritical reactor  Transient analyses  BELLA  Reactor safety  
Transient analyses for China initiative Accelerator Driven System using the extended BELLA code 期刊论文
ANNALS OF NUCLEAR ENERGY, 2023, 卷号: 190
Authors:  Wang, Guan;  Wallenius, Janne;  Yu, Rui;  Jiang, Wei;  Zhang, Lu;  Sheng, Xin;  Yun, Di;  Gu, L(顾龙)
Favorite  |    Submit date:2023/07/18
Codes (symbols)  Corrosion  Uranium dioxide  Accelerator driven system  Beam trip  BELLA  China initiative accelerator driven system  Engineering feasibility  Lead-bismuth eutectics  Reactor safety  Safety potential  Subcritical reactor  Transient analyze  
Finite element analysis of the main reactor vessel in the China Initiative Accelerator Driven System 期刊论文
ENGINEERING FAILURE ANALYSIS, 2023, 卷号: 146
Authors:  Wang, Di-Si;  Li, Song;  Zhang, You-Peng;  Liu, Bo;  Gu, L(顾龙);  Zhang, Lu;  Jiang, Wei;  Wallenius, Janne
Favorite  |    Submit date:2023/04/12
Accidents  Structural design  Academies of science  Accelerator driven system  ADINA  China initiative accelerator driven system  Effective stress  Fast-neutron reactors  Finite element analyse  Lead-bismuth eutectics  Liquid lead  Reactor-vessel  Finite Element Analysis  CiADS  Reactor Vessel  
Transient analyses for China initiative Accelerator Driven System using the extended BELLA code 期刊论文
ANNALS OF NUCLEAR ENERGY, 2023, 卷号: 190
Authors:  Wang, Guan;  Wallenius, Janne;  Yu, Rui;  Jiang, Wei;  Zhang, Lu;  Sheng, Xin;  Yun, Di;  Gu, L(顾龙)
Favorite  |    Submit date:2023/05/25
Codes (symbols)  Corrosion  Uranium dioxide  Accelerator driven system  Beam trip  BELLA  China initiative accelerator driven system  Engineering feasibility  Lead-bismuth eutectics  Reactor safety  Safety potential  Subcritical reactor  Transient analyze  
Axial expansion for prompt safety of a small lead-cooled reactor 会议论文
Annals of Nuclear Energy
Authors:  Zhang, You-Peng;  Wallenius, Janne;  Gu, L(顾龙);  Yang, Sheng;  Zhao, Yi-Yang;  Li, JY(李金阳);  Peng, Tian-Ji
Favorite  |    Submit date:2020/12/17
Expansion  Fast reactorsAxial expansion  Driver fuels  Fuel rods  Lead-cooled reactor  Metallic alloys  Minor actinide  Reactivity insertion