Speaker
C. F. Sang
Description
See the full Abstract at http://ocs.ciemat.es/EPS2018ABS/pdf/P5.1105.pdf
Effects of tungsten divertor baffling on plasma detachment during the
high power operation
C. F. Sang1, G. S. Xu2, L. Wang2, Q. Wang1, D. Z. Wang1
1
Key Laboratory of Materials Modification by Laser, Ion and Electron Beams (Ministry of
Education), School of Physics, Dalian University of Technology, Dalian, China
2
Institute of Plasma Physics, Chinese Academy of Sciences, Hefei, China
The steady-state operation of next-step fusion devices requires both the deposited heat flux
density on the divertor target below 10 MW/m2 and plasma temperature at the target below 5
eV to ensure adequate lifetime. Therefore, it will be essential to achieve highly dissipative or
detached divertor conditions for the control of heat flux and erosion in a fusion reactor. One
of the most effective methods to promote the achievement of detachment is to improve
neutral trapping and impurity screening in the divertor by changing the divertor structure [1].
Previous experiment and modeling works on JET, DIII-D, C-mod and JT-60U studies
highlight the importance of the divertor target shape and baffling on the plasma detachment
[1-6]. However, some critical questions still remain: (1) most of the previous works were
based on carbon-target, it is still unknown that whether it is still feasible for tungsten target?
(2) what is the range of input power that the current size tokamaks can operate leveraging the
benefits from a closed divertor? These question should be answered during the physical
design of the lower tungsten divertor of the Experimental Advanced Superconducting
Tokamak (EAST). In this work, the physical design of EAST lower divertor will be
presented, and a systematic analysis of the target shape and closure effects on the plasma
detachment is carried out by using SOLPS to address these questions.
References
[1] A. Loarte, Plasma Phys. Control. Fusion 43 (2001) R183.
[2] C. F. Sang, P.C. Stangeby et al., PPCF 59 (2017) 025009
[3] C. F. Sang, H. Y. Guo et al., Nucl. Fusion 57 (2017) 056043.
[4] H. Y. Guo, C. F. Sang et al., Nucl. Fusion 57 (2017) 044001
[5] B. Lipschultz et al., Fusion Sci. Technol. 51 (2007) 369.
[6] S. Tsuji et al., J. Nucl. Mater. 220-222 (1995) 400.
*This work was supported by National Key R&D Program of China No. 2017YFA0402500
and 2017YFE0300400, National Natural Science Foundation of China under Grant Nos.
11775044 and AHNFS under contract No. 1808085J07.
