Tritium recovery from an ITER ceramic test blanket module - process options and critical R&D issues

被引：23
|
作者：
Albrecht, H
Hutter, E
机构：
[1] Forschungszentrum Karlsruhe, Hauptabt Ingn Tech, D-76021 Karlsruhe, Germany
[2] Forschungszentrum Karlsruhe, Tritium Lab TLK, Hauptabt Versuchstech, D-76021 Karlsruhe, Germany
来源：
FUSION ENGINEERING AND DESIGN | 2000年 / 49-50卷
关键词：
tritium recovery; international thermonuclear experimental reactors; test blanket module; critical R&D issues;
D O I：
10.1016/S0920-3796(00)00183-6
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：
Tritium recovery from a ceramic breeder blanket has to be carried out under conditions characterized by large gas flow rates and very small concentrations of tritium, which is expected to be contained in the purge gas as HT and HTO. Several process options described in the literature have been evaluated with regard to their applicability to an international thermonuclear experimental reactor (ITER) test blanket module (TBM). This evaluation and the operational requirements of the ITER TBM are the basis of an additional process concept, which is described and discussed with respect to its critical R&D issues. (C) 2000 Elsevier Science B.V. All rights reserved.
引用
收藏
页码：769 / 773
页数：5
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