TRITIUM PROCESSING SYSTEM FOR THE ITER LI V BLANKET TEST MODULE/

Citation
Dk. Sze et al., TRITIUM PROCESSING SYSTEM FOR THE ITER LI V BLANKET TEST MODULE/, Fusion engineering and design, 39-4, 1998, pp. 859-864
Citations number
7
Categorie Soggetti
Nuclear Sciences & Tecnology
ISSN journal
09203796
Volume
39-4
Year of publication
1998
Pages
859 - 864
Database
ISI
SICI code
0920-3796(1998)39-4:<859:TPSFTI>2.0.ZU;2-Q
Abstract
The purpose of the ITER Blanket Testing Module is to test the operatin g and performance of candidate blanket concepts under a real fusion en vironment. To assure fuel self-sufficiency, the tritium breeding, reco very and processing have to be demonstrated. The tritium produced in t he blanket has to be processed to a purity which can be used for refue lling. All these functions need to be accomplished so that the tritium system can be scaled to a commercial fusion power plant from a safety and reliability point of view. This paper summarizes the tritium proc essing steps, the size of the equipment, power requirements, space req uirements, etc. for a self-cooled lithium blanket. This information is needed for the design and layout of the test blanket ancillary system and to assure that the ITER guidelines for remote handling of ancilla ry equipment can be met. (C) 1998 Published by Elsevier Science S.A. A ll rights reserved.