TRIO experiment

Technical Report · Sat Sep 01 00:00:00 EDT 1984

DOI:https://doi.org/10.2172/6126934· OSTI ID:6126934

Clemmer, R G; Finn, P A; Malecha, R F; Misra, B; Billone, M C; Bowers, D L; Fischer, A K; Greenwood, L R; Mattas, R F; Tam, S W

The TRIO experiment is a test of in-situ tritium recovery and heat transfer performance of a miniaturized solid breeder blanket assembly. The assembly (capsule) was monitored for temperature and neutron flux profiles during irradiation and a sweep gas flowed through the capsule to an anaytical train wherein the amounts of tritium in its various chemical forms were determined. The capsule was designed to operate at different temperatures and sweep gas conditions. At the end of the experiment the amount of tritium retained in the solid was at a concentration of less than 0.1 wppM. More than 99.9% of tritium generated during the experiment was successfully recovered. The results of the experiment showed that the tritium inventories at the beginning and at the end of the experiment follow a relationship which appears to be characteristic of intragranular diffusion.

• Research Organization: Argonne National Lab. (ANL), Argonne, IL (United States)
• DOE Contract Number: W-31-109-ENG-38
• OSTI ID: 6126934
• Report Number(s): ANL-84-55; ON: DE85008345; TRN: 85-007240
• Country of Publication: United States
• Language: English

Related Subjects

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