Please wait a minute...
Chin. Phys. B, 2020, Vol. 29(2): 025202    DOI: 10.1088/1674-1056/ab610d
PHYSICS OF GASES, PLASMAS, AND ELECTRIC DISCHARGES Prev   Next  

Discharge simulation and volt-second consumption analysis during ramp-up on the CFETR tokamak

Cheng-Yue Liu(刘成岳)1,2, Bin Wu(吴斌)2, Jin-Ping Qian(钱金平)2, Guo-Qiang Li(李国强)2, Ya-Wei Hou(侯雅巍)3, Wei Wei(韦维)1, Mei-Xia Chen(陈美霞)1, Ming-Zhun Lei(雷明准)2, Yong Guo(郭勇)2
1 Physics Department, School of Electronic Science&Applied Physics, Hefei University of Technology, Hefei 230601, China;
2 Institute of Plasma Physics, Chinese Academy of Science, Hefei 230026, China;
3 University of Science and Technology of China, Hefei 230031, China
Abstract  The plasma current ramp-up is an important process for tokamak discharge, which directly affects the quality of the plasma and the system resources such as volt-second consumption and plasma current profile. The China Fusion Engineering Test Reactor (CFETR) ramp-up discharge is predicted with the tokamak simulation code (TSC). The main plasma parameters, the plasma configuration evolution and coil current evolution are given out. At the same time, the volt-second consumption during CFETR ramp-up is analyzed for different plasma shaping times and different plasma current ramp rates dIP/dt with/without assisted heating. The results show that the earlier shaping time and the faster plasma current ramp rate with auxiliary heating will enable the volt-second to save 5%-10%. At the same time, the system ability to provide the volt-second is probably 470 V·s. These simulations will give some reference to engineering design for CFETR to some degree.
Keywords:  plasma current ramp-up      China Fusion Engineering Test Reactor      tokamak simulation code      volt-second consumption  
Received:  10 November 2019      Revised:  02 December 2019      Accepted manuscript online: 
PACS:  52.50.-b (Plasma production and heating)  
  52.55.Fa (Tokamaks, spherical tokamaks)  
  52.65.-y (Plasma simulation)  
Fund: Project supported by the National Key Research and Development Program of China (Grant Nos. 2017YFE0300500 and 2017YFE0300501), the National Natural Science Foundation of China (Grant Nos. 11875290 and 11875253), and the Fundamental Research Funds for the Central Universities of China (Grant No. WK3420000004).
Corresponding Authors:  Yong Guo     E-mail:  yguo@ipp.ac.cn

Cite this article: 

Cheng-Yue Liu(刘成岳), Bin Wu(吴斌), Jin-Ping Qian(钱金平), Guo-Qiang Li(李国强), Ya-Wei Hou(侯雅巍), Wei Wei(韦维), Mei-Xia Chen(陈美霞), Ming-Zhun Lei(雷明准), Yong Guo(郭勇) Discharge simulation and volt-second consumption analysis during ramp-up on the CFETR tokamak 2020 Chin. Phys. B 29 025202

[1] Song Y T, Wu S T, Li J G, Wan B N, Wan Y X, Fu P, Ye M Y, Zheng J X, Lu K, Gao X G, Liu S M, Liu X F, Lei M Z, Peng X B and Chen Y 2014 IEEE Trans. Plasma Sci. 42 503
[2] Jardin S C, Bell M G and Pomphrey N 1993 Nucl. Fusion 33 371
[3] Wu B 2002 Discharge Simulation of HT-7U Tokomak (PhD dissertation) (Hefei: Institute of Plasma Physics, Chinese Academy of Sciences) (in Chinese)
[4] Jardin S C, Pomphrey N and Delucia J L 1986 J. Comput. Phys. 66 481
[5] Guo Y, Xiao B J, Wu B and Liu C Y 2012 Plasma Phys. Control. Fusion 54 085022
[6] Liu C Y, Wu B, Xiao B J and Shu S B 2008 Plasma Sci. Technol. 10 8
[7] Jardin S C, Kessel C E and Pomphrey N 1994 Nucl. Fusion 34 1145
[8] Wu Bin and Zhang C 2003 Plasma Sci. Technol. 5 1625
[9] Menard J E, LeBlanc B, Sabbagh S A, Bell M, Bell R, Fredrickson E, Gates D, Jardin S, Kaye S, Kugel H, Maingi R, Maqueda R, Mueller D, Ono M, Paul S, Skinner C H, Stutman D and the NSTX Rearch Team 2001 Nucl. Fusion 41 1197
[10] Ejima, S, Callis R W, Luxon J L, Stambaugh R D, Taylor T S and Wesley J C 1982 Nucl. Fusion 22 1313
[11] Bandyopadhyay I, Ahmed S M, Atrey P K, Bhatt S B, Bhattacharya R, Chaudhury M B, Deshpande S P, Gupta C N, Jha R, Shankar J Y, Kumar V, Manchanda R, Raju D, Rao C V S, Vasu P and ADITYA Team 2004 Plasma Physical and Controlled Fusion 46 1443
[12] Kessel C E, Giruzzi G, Sips A C C, Budny R V, Artaud J F, Basiuk V, Imbeaux F, Joffrin E, Schneider M, Murakami M, Luce T, Holger S J, Oikawa T, Hayashi N, Takizuka T, Ozeki T, Na Y S, Park J M, Garcia J and Tucillo A A 2007 Nucl. Fusion 47 1274
[13] ITER Physics Basis Editors 1999 Nucl. Fusion 39 2137
[14] Kim S H, Bulmer R H, Campbell D J, Casper T A, LoDestro L L, Meyer W H, Pearlstein L D and Snipes J A 2016 Nucl. Fusion 56 126002
[15] Qiu Q L, Xiao B J, Guo Y, Liu L and Wang Y H 2017 Chin. Phys. B 26 065205
[16] Zheng J X, Liu X F, Song Y T, Lu K, Du S S and Feng C 2019 IEEE Trans. Appl. Supercond. 29 4600104
[1] A divertor plasma configuration design method for tokamaks
Yong Guo(郭勇), Bing-Jia Xiao(肖炳甲), Lei Liu(刘磊), Fei Yang(杨飞), Yuehang Wang(汪悦航), Qinglai Qiu (仇庆来). Chin. Phys. B, 2016, 25(11): 115201.
No Suggested Reading articles found!