Abstract
A facility was reconstructed for producing tritium in 40 TBq per batch. Gaseous tritium was extracted from neutron-irradiated6 Li-Al alloy targets by heating at 700 C under vacuum and collected in uranium. The recovery yield of tritium was about 100% and the isotopic purity of the product was about 95%. Through the production run, no leakage of tritium from the facility was observed.
Original language | English |
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Pages (from-to) | 198-203 |
Number of pages | 6 |
Journal | journal of nuclear science and technology |
Volume | 25 |
Issue number | 2 |
DOIs | |
Publication status | Published - 1988 Feb |
Keywords
- Facility
- Irradiation
- Lithium-aluminum alloy
- Neutron beams
- Purity
- Radio-isotope production
- Targets
- Tritium
- Tritium production
- Tritium recovery
ASJC Scopus subject areas
- Nuclear and High Energy Physics
- Nuclear Energy and Engineering