TRIO-01 experiment

Technical Report · Fri Feb 10 00:00:00 EST 1984

OSTI ID:5192853

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-31-109-ENG-38
• OSTI ID: 5192853
• Report Number(s): DOE/NBM-4009153; ON: DE84009153
• Resource Relation: Other Information: Paper copy only, copy does not permit microfiche production
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
ALUMINIUM OXIDES
TRITIUM RECOVERY
BREEDING BLANKETS
LITHIUM OXIDES
HEAT TRANSFER
IRRADIATION
ALKALI METAL COMPOUNDS
ALUMINIUM COMPOUNDS
CHALCOGENIDES
ENERGY TRANSFER
LITHIUM COMPOUNDS
OXIDES
OXYGEN COMPOUNDS
REACTOR COMPONENTS
RECOVERY
700206* - Fusion Power Plant Technology- Environmental Aspects