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Title: Conceptual design description for the tritium recovery system for the US ITER Li sub 2 O/Be water cooled blanket

Conference ·
OSTI ID:6310743
;  [1];  [2]
  1. Argonne National Lab., IL (USA)
  2. Battelle Pacific Northwest Lab., Richland, WA (USA)

The tritium recovery system for the US ITER Li{sub 2}O/Be water cooled blanket processes two separate helium purge streams to recovery tritium from the Li{sub 2}O zones and the Be zones of the blanket, to process the waste products, and to recirculate the helium back to the blanket. The components are selected to minimize the tritium inventory of the recovery system, and to minimize waste products. The system is robust to either an increase in the tritium release rate or to an in-leak of water in the purge system. Three major components were used to process these streams, first, 5A molecular sieves at {minus}196{degree}C separate hydrogen from the helium, second, a solid oxide electrolysis unit is used to reduce all molecular water, and third, a palladium/silver diffuser is used to ensure that only hydrogen (H{sub 2}, HT) species reach the cryogenic distillation unit. The total tritium process inventory is 20g. The total capital cost is {approximately}$14M. Technical advantages of a solid oxide electrolysis unit and a palladium/silver diffuser are presented. 5 refs., 1 fig., 3 tabs.

Research Organization:
Argonne National Lab., IL (USA)
Sponsoring Organization:
DOE/ER
DOE Contract Number:
W-31109-ENG-38
OSTI ID:
6310743
Report Number(s):
CONF-901007-53; ON: DE91006574; TRN: 91-001922
Resource Relation:
Conference: 9. topical meeting on technology of fusion energy, Oak Brook, IL (USA), 7-11 Oct 1990
Country of Publication:
United States
Language:
English