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Title: Modeling of divertor geometry effects in China fusion engineering testing reactor by SOLPS/B2-Eirene

The China Fusion Engineering Testing Reactor (CFETR) is currently under design. The SOLPS/B2-Eirene code package is utilized for the design and optimization of the divertor geometry for CFETR. Detailed modeling is carried out for an ITER-like divertor configuration and one with relatively open inner divertor structure, to assess, in particular, peak power loading on the divertor target, which is a key issue for the operation of a next-step fusion machine, such as ITER and CFETR. As expected, the divertor peak heat flux greatly exceeds the maximum steady-state heat load of 10 MW/m{sup 2}, which is a limit dictated by engineering, for both divertor configurations with a wide range of edge plasma conditions. Ar puffing is effective at reducing divertor peak heat fluxes below 10 MW/m{sup 2} even at relatively low densities for both cases, favoring the divertor configuration with more open inner divertor structure.
Authors:
 [1] ; ; ;  [2] ;  [1] ;  [3] ;  [4] ;  [1] ;  [3] ;  [5]
  1. School of Nuclear Science and Technology, University of Science and Technology of China, Hefei 230027 (China)
  2. Institute of Plasma Physics, Chinese Academy of Science, Hefei 230031 (China)
  3. (China)
  4. (United States)
  5. Alfven Laboratory, Royal Institute of Technology, Stockholm (Sweden)
Publication Date:
OSTI Identifier:
22252890
Resource Type:
Journal Article
Resource Relation:
Journal Name: Physics of Plasmas; Journal Volume: 21; Journal Issue: 5; Other Information: (c) 2014 AIP Publishing LLC; Country of input: International Atomic Energy Agency (IAEA)
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; CHINA; CONFIGURATION; DENSITY; DIVERTORS; GEOMETRY; HEAT FLUX; HEATING LOAD; ITER TOKAMAK; PEAK LOAD; PEAKS; PLASMA; SIMULATION; STEADY-STATE CONDITIONS; TESTING