American Nuclear Society
Home

Home / Publications / Journals / Fusion Science and Technology / Volume 19 / Number 3P2B

BEATRIX-II: In-Situ Tritium Test Operation

D. E. Baker, J. M. Miller, T. Kurasawa, O. D. Slagle

Fusion Science and Technology / Volume 19 / Number 3P2B / May 1991 / Pages 1640-1645

Material and Tritium / Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) / dx.doi.org/10.13182/FST91-A29576

The BEATRIX-II irradiation experiment is an in-situ tritium recovery experiment being carried out in the Fast Flux Test Facility (FFTF) reactor to evaluate the tritium release characteristics of fusion solid breeder materials. A sophisticated tritium gas handling system has been developed to continuously monitor the tritium recovery from the specimens and facilitate tritium removal from the experiment's sweep gas flow stream. The in-situ recovery experiment accommodates two different in-reactor specimen canisters with individual gas streams and temperature monitoring/control. Ionization chambers have been specifically designed to respond to the rapid changes in the tritium release rate at the anticipated tritium concentrations. Two ceramic electrolysis cells have proved effective in reducing the moisture in the gas streams to hydrogen/tritium. A tritium getter system, capable of reducing the tritium level by a factor greater than 4000, is used to reduce the tritium in the sweep gas to a level acceptable for release.