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.