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Implementation of CO2 and PbLi as working fluids in RELAP5/MOD3.3 towards accident analysis of COOL blanket for CFETR
期刊论文
FUSION ENGINEERING AND DESIGN, 2022, 卷号: 184
作者:
Wang, Wenjia
;
Cheng, Xiaoman
;
Yu, Yi
;
Wu, Qiuran
;
Liu, Songlin
收藏
  |  
浏览/下载:18/0
  |  
提交时间:2022/12/23
CFETR
COOL blanket
Accident analysis
Modified RELAP5
Investigation and Analysis on Tritium Accumulation Phenomenon Based on a Water-Cooled Blanket for CFETR at 1.5 GW
期刊论文
IEEE TRANSACTIONS ON PLASMA SCIENCE, 2022
作者:
Li, Jie
;
Zhang, Jie
;
Liu, Xiaogang
;
Gao, Xiang
收藏
  |  
浏览/下载:39/0
  |  
提交时间:2022/12/22
CFETR
temperature distribution
tritium accumulation
tritium release efficiency
tritium self-sufficiency
Preliminary design and analysis of the back supporting structure for CFETR WCCB blanket
期刊论文
FUSION ENGINEERING AND DESIGN, 2022, 卷号: 177
作者:
Xu, Kun
;
Lei, Mingzhun
;
Xu, Shuling
;
Wu, Qigang
;
Liu, Sumei
收藏
  |  
浏览/下载:18/0
  |  
提交时间:2022/05/16
CFETR
BSS
Attachment
Thermal-hydraulic analysis
Mechanical analysis
Quench Analysis of the CFETR TF Coil Using the Gandalf Code
期刊论文
IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY, 2021, 卷号: 31
作者:
Wen, Xinghao
;
Li, Junjun
;
Sang, Aiguo
;
Ren, Yong
;
Liu, Xiaogang
收藏
  |  
浏览/下载:57/0
  |  
提交时间:2021/04/26
China fusion engineering test reactor (CFETR)
quench
superconducting magnet
thermal-hydraulic
Transient analysis of TMSR-SF0 simulator
期刊论文
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2021, 卷号: 58, 期号: 3, 页码: 292-301
作者:
Wang, JJ
;
Dai, Y
;
Zou, Y
;
Xu, HJ
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  |  
浏览/下载:38/0
  |  
提交时间:2021/09/06
The thermal-hydraulic response of the superconducting outsert during the trip of the resistive magnet in the hybrid magnet system of the CHMFL
期刊论文
PHYSICA C-SUPERCONDUCTIVITY AND ITS APPLICATIONS, 2020, 卷号: 579
作者:
Jiang, Shili
;
Qian, Xinxing
;
Ding, Hangwei
;
Chen, Wenge
;
Chen, Zhiyou
收藏
  |  
浏览/下载:69/0
  |  
提交时间:2020/12/28
Cable-in-conduit conductors
Hybrid magnets
Thermal-hydraulic performance
Nb3sn
Superconducting magnet
Thermo-mechanical assessment of the optimized CFETR water cooled ceramic breeder blanket
期刊论文
FUSION ENGINEERING AND DESIGN, 2020, 卷号: 160
作者:
Ma, Xuebin
;
Cheng, Xiaoman
;
Liu, Songlin
;
Huang, Kai
收藏
  |  
浏览/下载:25/0
  |  
提交时间:2021/04/26
Thermal-hydraulic analysis
Thermo-mechanical analysis
WCCB blanket
CFETR
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
收藏
  |  
浏览/下载:71/0
  |  
提交时间:2019/11/26
Pressurized thermal shock
Large Break LOCA
Stress intensity factor
Reactor pressure vessel
Fracture mechanics
XFEM
Development and preliminary verification of code IMPC-transient
期刊论文
NUCLEAR ENGINEERING AND DESIGN, 2019, 卷号: 350, 页码: 137-146
作者:
Chen, Kang
;
Gao, Qingyu
;
Yang, Yongwei
;
Gao, Yucui
收藏
  |  
浏览/下载:52/0
  |  
提交时间:2019/11/10
ADANES
IMPC-transient
System safety analysis code
EBR-II SHRT
DAISY
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.
收藏
  |  
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
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