Design of ITER vacuum vessel in-wall shielding

被引:9
|
作者
Wang, X. [1 ]
Ioki, K. [1 ]
Morimoto, M. [2 ]
Choi, C. H. [1 ]
Utin, Y. [1 ]
Sborchia, C. [1 ]
TaiLhardat, O. [3 ]
Mille, B. [1 ]
Terasawa, A. [1 ]
Gribov, Y. [1 ]
Barabash, V. [1 ]
Polunovskiy, E. [1 ]
Dani, S. [1 ]
Pathak, H. [4 ]
Raval, J. [4 ]
Liu, S. [5 ]
Lu, M. [5 ]
Du, S. [5 ]
机构
[1] ITER Org, F-13115 St Paul Les Durance, France
[2] Mitsubishi Heavy Ind Co Ltd, Hyogo Ku, Kobe, Hyogo, Japan
[3] ZAC ST MARTIN, Assyst EOS, F-84120 Pertuis, France
[4] ITER India, Inst Plasma Res, Gandhinagar 382025, India
[5] Chinese Acad Sci, Inst Plasma Phys, Hefei, Peoples R China
关键词
ITER; Vacuum vessel; In-wall shielding; Design;
D O I
10.1016/j.fusengdes.2014.03.026
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 ITER vacuum vessel is a torus-shaped, double wall structure. The space between the double walls of the VV is filled with in-wall shielding (IWS) and cooling water. The main purpose of the in-wall shielding is to provide neutron shielding together with the blanket and VV shells and water during ITER plasma operation and to reduce the ripple of the Toroidal magnetic field. Based on ITER vacuum vessel structure and related requirements, in-wall shielding are designed as about 8900 individual blocks with different sizes and several different materials distributed over nine vessel sectors and nine field joints of vessel sectors. This paper presents the design of the IWS, considering loads, structural stresses and assembly method, and also shows neutron shielding effect and TF ripple reduced by the IWS. (C) 2014 Elsevier B.V. All rights reserved.
引用
收藏
页码:1814 / 1819
页数:6
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