Concept Design of Bi-2212 Superconducting Joint for the Central Solenoid Magnet of China Fusion Engineering Test Reactor

2020 ◽  
Vol 89 (9) ◽  
pp. 094201
Author(s):  
Haojun Yang ◽  
Kun Lu ◽  
Xiongyi Huang ◽  
Jian Rong ◽  
Yuntao Song
Keyword(s):  
Concept Design ◽  
Fusion Engineering ◽  
Test Reactor

scholarly journals Concept design of 100 kA hybrid DC breaker on China fusion engineering test reactor

2020 ◽  
Vol 158 ◽  
pp. 111740
Author(s):  
Hu Xingguang ◽  
Li Hua ◽  
Song Zhiquan ◽  
Ren Zhigang ◽  
Wang Shusheng ◽  
...  
Keyword(s):  
Concept Design ◽  
Dc Breaker ◽  
Fusion Engineering ◽  
Test Reactor

Designing the X-divertor configurations for the China Fusion Engineering Test Reactor

2020 ◽  
Vol 62 (10) ◽  
pp. 105007
Author(s):  
H Li ◽  
G Q Li ◽  
X J Liu ◽  
H Xie ◽  
J P Qian ◽  
...  
Keyword(s):  
Fusion Engineering ◽  
Test Reactor

Steady State and Transient Analysis of Novel Design Helium Cooled Ceramic Blanket (HCCB) System of China Fusion Engineering Test Reactor (CFETR)

2018 ◽  
Vol 37 (6) ◽  
pp. 308-316 ◽  
Author(s):  
Salah Ud-Din Khan ◽  
Jian Wang ◽  
Yuntao Song ◽  
Shahab Ud-Din Khan ◽  
Usman Ali Rana ◽  
...  
Keyword(s):  
Steady State ◽  
Transient Analysis ◽  
Fusion Engineering ◽  
Test Reactor ◽  
Novel Design

R&D of Full-Scale Partial Vacuum Vessel Mockup for Future Fusion Engineering Test Reactor in China

2015 ◽  
Vol 34 (3) ◽  
pp. 666-670 ◽  
Author(s):  
Ma Jianguo ◽  
Wu Jiefeng ◽  
Liu Zhihong ◽  
Fan Xiaosong
Keyword(s):  
Full Scale ◽  
Vacuum Vessel ◽  
Fusion Engineering ◽  
Test Reactor ◽  
Partial Vacuum

Thermal hydraulic analysis of China fusion engineering test reactor during thermal quenching by comparative approach of Relap5 and THEATRe codes

2016 ◽  
Vol 30 (30) ◽  
pp. 1650357 ◽  
Author(s):  
Salah Ud-Din Khan ◽  
Yuntao Song ◽  
Shahab Ud-Din Khan
Keyword(s):  
Thermal Quenching ◽  
Reactor Power ◽  
Comparative Approach ◽  
Hydraulic Analysis ◽  
Reactor Operation ◽  
Safe Operation ◽  
Tokamak Reactor ◽  
Fusion Engineering ◽  
Test Reactor ◽  
Thermal Hydraulic Analysis

Thermal quenching in Tokamak reactor is the most obvious phenomenon happens during plasma disruption conditions. The current research is focused on the thermal behavior of different parameters of China fusion engineering test reactor (CFETR) including reactor power, pressure and mass flow rate conditions. The analysis was performed by two thermal hydraulic codes, i.e. THEATRe and Relap5. During the first phase of research, thermal quenching behavior and trends that can be possible during the reactor operation was performed. In the next phase, nodalization diagram of THEATRe and Relap5 codes were developed. The listed parameters were calculated and analyzed for the safety aspects of the reactor. The main objective of the research was to analyze the blanket system of CFETR (Tokamak) for safety concerns during disruption condition. The research will be extended to other components for safe operation of reactor as well.

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