Tokamak dust, characterisation and removal studies

被引:9
作者
Wykes, M
Counsell, G
McGlinchey, D
Wu, CH
机构
[1] UKAEA Euratom Fus Assoc, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England
[2] Glasgow Caledonian Univ, GPE, BSH Ltd, Glasgow G4 0BA, Lanark, Scotland
[3] EFDA, Close Support Unit, IPP Garching, D-85748 Garching, Germany
关键词
tokamak; vibratory conveying; surrogate material;
D O I
10.1016/S0920-3796(01)00578-6
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
Dust and flakes are generated during operation of next step tokamaks such as ITER by plasma interaction with plasma facing components. Accumulation of this particulate engenders potential safety problems, the main ones being chemical reactivity (hydrogen), mobilisation of radioactive dust in a loss of vacuum event, and tritium retention within the plasma chamber. The present prediction for the annualised particulate generation rate is many times more than the currently foreseen safety limits for in-vessel dust inventory. Thus, means may have to be provided to remove particulate on a routine basis. If a vacuum break is needed for batch particulate removal, the resulting reduction in tokamak availability may be unacceptable. Ideally, means should be provided to collect and remove particulate without breaking the vacuum, on a quasi-continuous, intra-shot basis. Vibratory conveying (VC) is one approach to particulate removal. This paper reports initial characterisation of surrogate materials used to emulate tokamak particulate, preliminary results from a small-scale VC test rig, and concepts for implementing VC in a tokamak, (C) 2001 UKAEA. Published by Elsevier Science Ltd. All rights reserved.
引用
收藏
页码:403 / 407
页数:5
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