Tritium and heat management in ITER Test Blanket Systems port cell for maintenance operations

被引：11

作者：

Giancarli, L. M. ^{[1
]}

Cortes, P. ^{[1
]}

Iseli, M. ^{[1
]}

Lepetit, L. ^{[1
]}

Levesy, B. ^{[1
]}

Livingston, D. ^{[2
]}

Neviere, J. C. ^{[3
]}

Pascal, R. ^{[1
]}

Ricapito, I. ^{[4
]}

Shu, W. ^{[1
]}

Wyse, S. ^{[2
]}

机构：

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

[2] Frazer Nash Consultancy Ltd, Dorking RH4 1HJ, Surrey, England

[3] Comex Nucl, F-13115 St Paul Les Durance, France

[4] Fus Energy, E-08019 Barcelona, Spain

来源：

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

关键词：

ITER; TBM; Breeding blanket; Tritium management;

D O I：

10.1016/j.fusengdes.2014.01.059

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：

Three ITER equatorial port cells are dedicated to the assessment of six different designs of breeding blankets, known as Test Blanket Modules (TBMs). Several high temperature components and pipework will be present in each TBM port cell and will release a significant quantity of heat that has to be extracted in order to avoid the ambient air and concrete wall temperatures to exceed allowable limits. Moreover, from these components and pipes, a fraction of the contained tritium permeates and/or leaks into the port cell. This paper describes the optimization of the heat extraction management during operation, and the tritium concentration control required for entry into the port cell to proceed with the required maintenance operations after the plasma shutdown. (C) 2014 L.M. Giancarli. Published by Elsevier B.V. All rights reserved.

引用

页码：2088 / 2092

页数：5

共 4 条

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