Nuclear engineering of diagnostic port plugs on ITER

被引:12
|
作者
Pitcher, C. S. [1 ]
Barnsley, R. [1 ]
Feder, R. [2 ]
Hu, Q. [3 ]
Loesser, G. D. [2 ]
Lyublin, B. [4 ]
Padasalagi, S. [5 ]
Pak, S. [6 ]
Reichle, R. [1 ]
Sato, K. [7 ]
Udintsev, V. S. [1 ]
Walker, C. [1 ]
Walsh, M. [1 ]
Zhai, Y. [2 ]
机构
[1] ITER Org, F-13115 St Paul Les Durance, France
[2] Princeton Plasma Phys Lab, Princeton, NJ 08543 USA
[3] Chinese Acad Sci, Inst Plasma Phys, Beijing 100864, Peoples R China
[4] Efremov, St Petersburg, Russia
[5] Inst Plasma Res, Gandhinagar, Gujarat, India
[6] Natl Fus Res Inst, Taejon, South Korea
[7] Japan Atom Energy Agcy, Naka, Ibaraki, Japan
关键词
ITER; Diagnostics; Port plugs; Nuclear shielding; Shut-down dose rate; Remote handling; DESIGN;
D O I
10.1016/j.fusengdes.2012.01.043
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 nuclear engineering infrastructure of port-based diagnostics on ITER is presented, including the equatorial and upper port plug generic designs, the adopted modular concept, the loads and associated load response and the remote handling. A modular approach is adopted for the internal shielding modules as this helps to reduce the dominant electromagnetic loads, reduces interfaces and accelerates remote handling. Extensive use of gun-drilling is employed to produce water channels in the stainless steel plate and forgings used to construct the port plugs and modules. The French Nuclear Code RCC-MR (2007) is employed in the design and the manufacturing. An integrated remote handling scheme is described, including a description of maintenance operations in the Hot Cell Facility. (C) 2012 Published by Elsevier B.V.
引用
收藏
页码:667 / 674
页数:8
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