Autor: |
S.W. Tam, A.E. Scandora, Michael C. Billone, Albert K. Fischer, Patricia A. Finn, R.G. Clemmer, B. Misra, Carl E. Johnson |
Rok vydání: |
1985 |
Předmět: |
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Zdroj: |
Journal of Nuclear Materials. :171-175 |
ISSN: |
0022-3115 |
DOI: |
10.1016/0022-3115(85)90128-x |
Popis: |
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 analytical 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. |
Databáze: |
OpenAIRE |
Externí odkaz: |
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