Preliminary design of lithium lead test blanket module for the Chinese experimental advanced superconducting Tokamak

被引：8
作者：
Liu, Songlin [1 ]
Bai, Yunqing [1 ]
Zheng, Shanliang [1 ]
Chen, Hongli [1 ]
Wang, Weihua [1 ]
Long, Pengcheng [1 ]
Wu, Yican [1 ]
机构：
[1] Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Peoples R China
来源：
FUSION ENGINEERING AND DESIGN | 2007年 / 82卷 / 15-24期
关键词：
ITER; EAST device; breeding blanket; EAST-TBM;
D O I：
10.1016/j.fusengdes.2007.07.041
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 Chinese Experimental Advanced Superconducting Tokamak (EAST) has been successfully constructed and has produced a discharge of plasma in x 2006. It aims to achieve static-state operation of high performance D-D plasma with a long pulse of up to 1000 s and may be severed as a valuable pre-testing platform for Test Blanket Module (TBM) prior to International Thermonuclear Experimental Reactor (ITER). Based on the Chinese Dual Function Lithium Lead TBM (DFLL-TBM) design and its testing plan for ITER and EAST, a lithium lead test blanket module concept for the EAST (EAST-TBM) has been proposed as an important R&D activity and is expected to be tested in EAST focusing on electro-magnetics and thermo-mechanics performances of the TBM, including the influence of TBM made of ferromagnetic steel on tokamak plasma. This paper presents the status of EAST-TBM design, including design guideline, main features, instrumentation configuration, and installation in EAST port. The feasibility of the EAST-TBM has been validated with the preliminary performance analyses. (C) 2007 Elsevier B.V. All rights reserved.
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收藏
页码：2347 / 2352
页数：6
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