TY - JOUR
T1 - Design, analysis and R and D of the EAST In-vessel components
AU - Yao, Damao
AU - Bao, Liman
AU - Li, Jiangang
AU - Song, Yuntao
AU - Chen, Wenge
AU - Du, Shijun
AU - Hu, Qingsheng
AU - Wei, Jing
AU - Xie, Han
AU - Liu, Xufeng
AU - Cao, Lei
AU - Zhou, Zibo
AU - Chen, Junling
AU - Mao, Xinqiao
AU - Wang, Shengming
AU - Zhu, Ning
AU - Weng, Peide
AU - Wan, Yuanxi
PY - 2008/6/1
Y1 - 2008/6/1
N2 - In-vessel components are important parts of the EAST superconducting tokamak. They include the plasma facing components, passive plates, cryo-pumps, in-vessel coils, etc. The structural design, analysis and related R&D have been completed. The divertor is designed in an up-down symmetric configuration to accommodate both double null and single null plasma operation. Passive plates are used for plasma movement control. In-vessel coils are used for the active control of plasma vertical movements. Each cryo-pump can provide an approximately 45 m3/s pumping rate at a pressure of 10-1 Pa for particle exhaust. Analysis shows that, when a plasma current of 1 MA disrupts in 3 ms, the EM loads caused by the eddy current and the halo current in a vertical displacement event (VDE) will not generate an unacceptable stress on the divertor structure. The bolted divertor thermal structure with an active cooling system can sustain a load of 2 MW/m2 up to a 60 s operation if the plasma facing surface temperature is limited to 1500 °C. Thermal testing and structural optimization testing were conducted to demonstrate the analysis results.
AB - In-vessel components are important parts of the EAST superconducting tokamak. They include the plasma facing components, passive plates, cryo-pumps, in-vessel coils, etc. The structural design, analysis and related R&D have been completed. The divertor is designed in an up-down symmetric configuration to accommodate both double null and single null plasma operation. Passive plates are used for plasma movement control. In-vessel coils are used for the active control of plasma vertical movements. Each cryo-pump can provide an approximately 45 m3/s pumping rate at a pressure of 10-1 Pa for particle exhaust. Analysis shows that, when a plasma current of 1 MA disrupts in 3 ms, the EM loads caused by the eddy current and the halo current in a vertical displacement event (VDE) will not generate an unacceptable stress on the divertor structure. The bolted divertor thermal structure with an active cooling system can sustain a load of 2 MW/m2 up to a 60 s operation if the plasma facing surface temperature is limited to 1500 °C. Thermal testing and structural optimization testing were conducted to demonstrate the analysis results.
KW - EAST superconducting tokamak
KW - In-vessel components
KW - Related R and D
KW - Structure design and analyses
KW - Thermal analyses
UR - https://www.scopus.com/pages/publications/47749109482
U2 - 10.1088/1009-0630/10/3/20
DO - 10.1088/1009-0630/10/3/20
M3 - 文章
AN - SCOPUS:47749109482
SN - 1009-0630
VL - 10
SP - 367
EP - 372
JO - Plasma Science and Technology
JF - Plasma Science and Technology
IS - 3
ER -