TRIO-01 experiment: in-situ tritium recovery results

Conference · Sat Jan 01 04:00:00 EST 1983

OSTI ID:5435517

Clemmer, R G; Finn, P A; Billone, M C; Misra, B; Greenwood, L R; Dyer, F F; Dudley, I T; Bate, L C; Clemmer, E D; Fisher, P W

The TRIO-01 experiment was designed to test in-situ tritium recovery and heat transfer performance of a candidate solid breeder, ..gamma..-LiAlO/sub 2/. The results showed that nearly all the tritium generated was recovered. Only < 0.1 wppM tritium remained in the solid after irradiation testing. The heat transfer performance showed that temperature profiles can be effectively controlled.

• Research Organization: Argonne National Lab., IL (USA); Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 5435517
• Report Number(s): CONF-831203-35; ON: DE84004003
• Country of Publication: United States
• Language: English

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ALKALI METAL COMPOUNDS
ALUMINIUM COMPOUNDS
ALUMINIUM OXIDES
BREEDING BLANKETS
CHALCOGENIDES
ENERGY TRANSFER
HEAT TRANSFER
IRRADIATION
LITHIUM COMPOUNDS
LITHIUM OXIDES
OXIDES
OXYGEN COMPOUNDS
REACTOR COMPONENTS
RECOVERY
TRITIUM RECOVERY