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

Tritium recovery from a ceramic breeder blanket has to be carried out under conditions characterized by large gas flow rates and very small concentrat ions of tritium, which is expected to be contained in the purge gas as HT a nd HTO. Several process options described in the literature have been evalu ated with regard to their applicability to an international thermonuclear e xperimental reactor (ITER) test blanket module (TBM). This evaluation and t he operational requirements of the ITER TBM are the basis of an additional process concept, which is described and discussed with respect to its criti cal R&D issues. (C) 2000 Elsevier Science B.V. All rights reserved.