Production of 40 TBq tritium using neutron-irradiated6li-al alloy

Masakazu Tanase; Mineo Kato; Kiyoyuki Kurosawa; Shoji Motoishi; Shogo Okane; Hiroyuki Sugai; Makoto Fujie; Katsuyuki Onoma; Hisamichi Yamabayashi

doi:10.1080/18811248.1988.9733576

Production of 40 TBq tritium using neutron-irradiated₆li-al alloy

Masakazu Tanase, Mineo Kato, Kiyoyuki Kurosawa, Shoji Motoishi, Shogo Okane, Hiroyuki Sugai, Makoto Fujie, Katsuyuki Onoma, Hisamichi Yamabayashi

ENG - Quantum Science and Energy Engineering

Research output: Contribution to journal › Article › peer-review

8 Citations (Scopus)

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
Pages (from-to)	198-203
Number of pages	6
Journal	journal of nuclear science and technology
Volume	25
Issue number	2
DOIs	https://doi.org/10.1080/18811248.1988.9733576
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

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Production of 40 TBq tritium using neutron-irradiated₆li-al alloy. / Tanase, Masakazu; Kato, Mineo; Kurosawa, Kiyoyuki; Motoishi, Shoji; Okane, Shogo; Sugai, Hiroyuki; Fujie, Makoto; Onoma, Katsuyuki; Yamabayashi, Hisamichi.

In: journal of nuclear science and technology, Vol. 25, No. 2, 02.1988, p. 198-203.

Research output: Contribution to journal › Article › peer-review

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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.",

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AU - Okane, Shogo

AU - Sugai, Hiroyuki

AU - Fujie, Makoto

AU - Onoma, Katsuyuki

AU - Yamabayashi, Hisamichi

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