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

Journal Article · · Plasma Physics and Controlled Fusion
 [1];  [2];  [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)
+ Show Author Affiliations
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.
Research Organization:
Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)
Sponsoring Organization:
USDOE
Contributing Organization:
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).; 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
OSTI ID:
1341359
Alternate ID(s):
OSTI ID: 22717520
Journal Information:
Plasma Physics and Controlled Fusion, Journal Name: Plasma Physics and Controlled Fusion Journal Issue: 2 Vol. 59; ISSN 0741-3335
Publisher:
IOP ScienceCopyright Statement
Country of Publication:
United States
Language:
English

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Cited By (1)

Effect of ∇ B drift on the H-mode power threshold in upper single null plasmas with ITER-like tungsten divertor on EAST journal July 2018

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Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
TFTR
fast ion loss
neutral beam heating
particles
tokamaks
toroidal field ripple
transport