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

Journal Article · Thu May 15 04:00:00 EDT 2014 · Physics of Plasmas

DOI:https://doi.org/10.1063/1.4875721· OSTI ID:22252890

Chen, Y. P.; Li, G. Q.; Luo, Z. P. ^[1]; Guo, H. Y. ^[2]; Ye, M. Y. ^[2]; Tendler, M. ^[3]

---

1. Institute of Plasma Physics, Chinese Academy of Science, Hefei 230031 (China)
2. School of Nuclear Science and Technology, University of Science and Technology of China, Hefei 230027 (China)
3. Alfven Laboratory, Royal Institute of Technology, Stockholm (Sweden)

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.

• OSTI ID: 22252890
• Journal Information: Physics of Plasmas, Journal Name: Physics of Plasmas Journal Issue: 5 Vol. 21; ISSN PHPAEN; ISSN 1070-664X
• Country of Publication: United States
• Language: English

Related Subjects

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