Lithium test module on ITER/TIBER

ITER/TIBER (ITER) is the U.S. version of the design for the International Thermonuclear Experimental Reactor. The role of ITER is to test nuclear components for fusion power reactors. A major nuclear component to be tested is the breeder blanket and its associated tritium recovery system. To assist in the design of ITER, the engineering design of different blanket systems was done. This report summarizes a design of the tritium recovery system for a liquid lithium blanket, a prime candidate for a fusion power reactor. Objectives of this design were to ensure that a reliable, integrated performance of the tritium recovery system could be demonstrated and that the tritium could be measured. The latter objective permits one to validate the performance of the blanket module. For the tritium recovery system, the contractors and the electrolysis units were sized and costed. The magnetic force on the contactor was assessed. The tritium inventory for the system and the blanket module was calculated. Tritium recovery systems for larger blanket units could be designed using the information developed in this report