An approach to explore the eddy currents of the new type divertor for EAST device using ANSYS code

Changle Liu1, Dongrui Yao1, J. Doody1, B. Lipschultz2, Longfei Zhou2, Chao Liang1, Zibo Zhou1, Lei Cao1, Tianheng Xu1
1Institute of Plasma Physics, Chinese Academy of Sciences, Hefei, China
2Plasma Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, USA

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Tài liệu tham khảo

Wan Y X. Overview of steady state operation of HT-7 and present status of the HT-7U project. Nucl Fusion, 2000, 40(6): 1057–1068

Wan B N. Recent experiments in the EAST and HT-7 superconducting tokamaks, Nucl Fusion, 2009, 49(10): 104011

Guo H Y, Gao X, Li J, et al. Recent progress on divertor operations in EAST. J Nucl Mater, 2011, 415(1): 369–374

Guo H Y, Chen Y P, Liu S C, et al. Effect of magnetic geometry on divertor asymmetry and access to high confinement mode in EAST. J Nucl Mater, 2013, http://dx.doi.org/10.1016/j.jnucmat.2013.01.047

Chen L, Wen W D, Cui H T. Generalization of Hill’s yield criterion to tension-compression asymmetry materials. Sci China Tech Sci, 2013, 56: 89–97

Liu W T, Zhang Y, Feng Z J, et al. Effects of stick-slip on stress intensity factors for subsurface short cracks in rolling contact. Sci China Tech Sci, 2013, 56: 2413–2421

Deng S, Han X H, Qin X P, et al. Subsurface crack propagation under rolling contact fatigue in bearing ring. Sci China Tech Sci, 2013, 56: 2422–2432

Giesen B, Neubauer O, Bondarchuk E, et al. Panin. Investigation of eddy currents in the components of the dynamic ergodic divertor of TEXTOR using analytical and numerical approaches. Fusion Eng Des, 2003, 66–68: 419–423

Bandyopadhyay I, Deshpande S P, Chaturvedi S, et al. Design analysis of plasma position control in SST1. Fusion Eng Des, 2001, 54(2): 151–166

Jhang H, Kessel C, Pomphrey N, et al. Design calculations for fast plasma position control in Korea Superconducting Tokamak Advanced Research. Fusion Eng Des, 1999, 45(1): 101–115

Alekseev A, Arslanova D, Belovet A, et al. Computational models for electromagnetic transients in ITER vacuum vessel, cryostat and thermal shield. Fusion Eng Des, http://dx.doi.org/10.1016/j.fusengdes . 2013.01.102

Yao D M, Li J G, Song Y T, et al. EAST in-vessel components design. Fusion Eng Des, 2005, 75–79: 491–494

Song Y T, Peng X B, Xie H, et al. Plasma facing components of EAST. Fusion Eng Des, 2010, 85(10–12): 2323–2327

Janeschitz G, Tivey R, Antipenkov A, et al. Overview of the divertor design and its integration into RTO: RC-ITER. Fusion Eng Des, 2000, 49–50: 107–117

Zhu Y F, Liu C L, Liu, X F, et al. Design and analysis of the thermal shield of the prototype superconducting dipole magnet for GSI. IEEE T Appl Supercond, 2013, 23(2): 4001108

Liu X F, Du S J, Yao D M, et al. The design, analysis and alignment of EAST divertor. Fusion Eng Des, 2009, 84(1): 78–82

Du S J, Wang L H, Liu X F, et al. Electromagnetic analysis of the passive stabilizers for EAST. Fusion Eng Des, 2006, 81(19): 2267–2273

Doody J, Granets, Lipschultz B, et al. ANSYS model to predict magnetic fields and loads in Alcator C-Mod’s new outer divertor during a disruption. ANS 20th Topical Meeting on the Technology of Fusion Energy (TOFE 2012), Nashville, USA, 2012