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

Journal Article · · Plasma Physics and Controlled Fusion
 [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)
+ 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 Lab. (PPPL), Princeton, NJ (United States)
Sponsoring Organization:
USDOE
Contributing Organization:
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).
Grant/Contract Number:
No DOE funding: 2013GB101001; 2014DFG61950; 11405212; 11628509
OSTI ID:
1341359
Journal Information:
Plasma Physics and Controlled Fusion, Vol. 59, Issue 2; ISSN 0741-3335
Publisher:
IOP ScienceCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 27 works
Citation information provided by
Web of Science

References (15)

Simulation on Heating and Current Drive Using Neutral Beam Injection with Variable Injection Angle on EAST journal June 2010
Phenomenology of energetic-ion loss from the DIII-D tokamak journal July 2010
Fast particle losses due to NTMs and magnetic field ripple journal February 2008
Perturbative study of energetic particle redistribution by Alfvén eigenmodes in ITER journal December 2012
Collisional stochastic ripple diffusion of alpha particles and beam ions on TFTR journal October 1995
Theory of mode-induced beam particle loss in tokamaks journal January 1983
The tokamak Monte Carlo fast ion module NUBEAM in the National Transport Code Collaboration library journal June 2004
Kinetic equilibrium reconstruction on EAST tokamak journal November 2013
Effect of radial electric field and ripple on edge neutral beam ion distribution in ASDEX Upgrade journal February 2008
Enhanced transport in tokamaks due to toroidal ripple journal January 1980
Fast ion losses due to toroidal field ripple in JT-60U journal August 1994
Confinement of High-Energy Trapped Particles in Tokamaks journal August 1981
Simulations of alpha particle ripple loss from the International Thermonuclear Experimental Reactor journal August 1996
Study of stochastic toroidal field ripple losses of charged fusion products at the midplane of TFTR journal March 1993
Numerical analysis of the effect of fast-ion losses on plasma rotation in a tokamak with toroidal field ripple journal July 2008

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
neutral beam heating
toroidal field ripple
fast ion loss
tokamaks
particles
transport
TFTR