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Title: Calculation of prompt loss and toroidal field ripple loss under neutral beam injection on EAST

Here, neutral beam injection is a major auxiliary heating method in the EAST experimental campaign. This paper gives detailed calculations of beam loss with different plasma equilibria using the guiding center code ORBIT and NUBEAM/TRANSP. Increasing plasma current can dramatically lower the beam ion prompt loss and ripple loss. Countercurrent beam injection gives a much larger prompt loss fraction than co-injection, and ripple-induced collisionless stochastic diffusion is the dominant loss channel.
Authors:
 [1] ;  [2] ; ORCiD logo [3] ;  [1] ;  [1] ;  [1] ;  [4]
  1. Chinese Academy of Sciences (CAS), Hefei (People's Republic of China)
  2. Chinese Academy of Sciences (CAS), Hefei (People's Republic of China); Univ. of Science and Technology of China, Hefei (People's Republic of China); Princeton Univ., Princeton, NJ (United States)
  3. Princeton Univ., Princeton, NJ (United States)
  4. Chinese Academy of Sciences (CAS), Hefei (People's Republic of China); Univ. of Science and Technology of China, Hefei (People's Republic of China)
Publication Date:
Grant/Contract Number:
No DOE funding: 2013GB101001; 2014DFG61950; 11405212; 11628509
Type:
Accepted Manuscript
Journal Name:
Plasma Physics and Controlled Fusion
Additional Journal Information:
Journal Volume: 59; Journal Issue: 2; Journal ID: ISSN 0741-3335
Publisher:
IOP Science
Research Org:
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Sponsoring Org:
USDOE
Contributing Orgs:
Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031, People's Republic of China; University of Science and Technology of China, Hefei 230026, People's Republic of China; This work was supported by the National Magnetic Confinement Fusion Science Program of China (Contract No. 2013GB101001), the International Science & Technology Cooperation Program of China (Contract No. 2014DFG61950), and the National Natural Science Foundation of China (Contract Nos. 11628509 and 11405212).
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; neutral beam heating; toroidal field ripple; fast ion loss; tokamaks; particles; transport; TFTR
OSTI Identifier:
1341359