Status of ITER TBM port plug conceptual design and analyses

被引：21

作者：

Kim, Byoung Yoon ^{[1
]}

Sabourin, Flavien ^{[1
]}

Merola, Mario ^{[1
]}

Giancarli, Luciano ^{[1
]}

Villari, R. ^{[2
]}

Di Maio, P. A. ^{[3
]}

Lucca, F. ^{[4
]}

Marconi, M. ^{[4
]}

Levesy, B. ^{[1
]}

机构：

[1] ITER Org, F-13115 St Paul Les Durance, France

[2] ENEA Frascati, Rome, Italy

[3] Univ Palermo, I-90133 Palermo, Italy

[4] LTCalcoli, I-23807 Merate, Italy

来源：

FUSION ENGINEERING AND DESIGN | 2014年 / 89卷 / 9-10期

关键词：

ITER; Tokamak; Plasma facing components; TBM port plug (TBM PP);

D O I：

10.1016/j.fusengdes.2014.01.017

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 test blanket module port plug (TBM PP) consists of a TBM frame and two TBM-sets. However, at any time of the ITER operation, a TBM set can be replaced by a dummy TBM. The frame provides a standardized interface with the vacuum vessel (VV)/port structure and provides thermal isolation from the shield blanket. As one of the plasma-facing components, it shall withstand heat loads while at the same time provide adequate neutron shielding for the W and magnet coils. The frame design shall provide a stable engineering solution to hold TBM-sets and also provide a mean for rapid remote handling replacement and refurbishment. This paper presents main design features of the conceptual design of TBM PP with two dummy TBMs. Also analysis results are summarized to evaluate shielding, hydraulic, and thermal and structural performances of the TBM PP design. (C) 2014 ITER Organization. Published by Elsevier B.V. All rights reserved.

引用

页码：1969 / 1974

页数：6

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