Progress on the ITER TBM port plug design

被引:3
作者
Kim, Byoung-Yoon [1 ]
Marconi, Matteo [2 ]
Neviere, Jean-Christophe [3 ]
Merola, Mario [1 ]
Giancarli, Luciano M. [1 ]
Lucca, Flavio [2 ]
Gicquel, Stefan [1 ]
机构
[1] ITER Org, F-13067 St Paul Les Durance, France
[2] LTCalcoli, I-23807 Merate, Italy
[3] Comex Nucl, F-13115 St Paul Les Durance, France
关键词
ITER; Test blanket module (TBM); TBM port plug (TBM PP); Vacuum vessel (VV); Metallic gasket;
D O I
10.1016/j.fusengdes.2015.06.040
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
In three of the ITER equatorial ports, tritium breeding blanket concepts will be validated and tested using mock-up breeding blankets called test blanket modules (TBM). In these ports, two TBM-Sets are mechanically attached in a TBM Frame to form a TBM port plug (TBM PP). The ITER Organization is responsible for the design and manufacture of both this TBM Frame and the Dummy TBMs which will fill them. As a part of this development, in 2013, a conceptual design review (CDR) of TBM PP with two dummy TBMs revealed the need for improvement of design performance, interfaces and maintainability. This paper presents the main design improvements after the CDR as well as associated feasibility analysis of the improved design focusing on the attachment. Finally the work plan for the Preliminary Design phase is summarized. (C) 2015 Elsevier B.V. All rights reserved.
引用
收藏
页码:1509 / 1514
页数:6
相关论文
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[2]  
Luciano L. M., 2012, FUSION ENG DES, V87, P395
[3]  
Villari R., 2014, 28 S FUS TECHN