Ripple effect and impact of test blanket module by using RAFM steels on the plasma of ITER

被引：6
作者：
Liu, Songlin [1 ,2 ]
Liu, Yang [1 ,2 ]
Wang, Weihua [1 ]
Lu, Ruojun [1 ,2 ]
Jin, Ming [1 ,2 ]
Zeng, Qin [1 ,2 ]
机构：
[1] Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Anhui, Peoples R China
[2] Univ Sci & Technol China, Sch Nucl Sci & Technol, Hefei 230027, Anhui, Peoples R China
来源：
FUSION ENGINEERING AND DESIGN | 2009年 / 84卷 / 7-11期
基金：
中国国家自然科学基金;
关键词：
International Thermonuclear Experimental Reactor; Plasma; Toroidal field ripple; Test blanket module; ACTIVATION MARTENSITIC STEEL; CONCEPTUAL DESIGN; CHINA; PROGRESS; STRATEGY;
D O I：
10.1016/j.fusengdes.2009.01.062
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
The losses of high-energy particles from the plasma depend on the toroidal field (TF) ripple in Tokomak machine. TBM (test blanket module). using RAFM (reduced activation ferritic/martensitic) steels as structure material, impacts oil TF ripple in International Thermonuclear Experimental Reactor (ITER). The aim in this paper was to investigate the impact of TBM oil TF ripple in ITER. It was analyzed based on ANSYS code and the Chinese DFLL (Dual Function Lithium Lead)-TBM as instances of analysis. The results indicated the TF ripple was still beyond the acceptable level of ITER (delta(TF) < 0.3%) while considering several kinds of configurations (different masses, different dimensions, and different distances to plasma) of the DFLL-TBM. The correction coil might be one way to further reduce the effect on ripple of TF. and the ferromagnetic inserts under TF coil need to continue optimized. (C) 2009 Elsevier B.V. All rights reserved.
引用
收藏
页码：1206 / 1213
页数：8
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