A Fast Neutron, In Situ Tritium Recovery Experiment on Solid Breeder Materials

G. W. Hollenberg; T. Kurasawa; H. Watanabe; S. E. Berk; I. J. Hastings; J. Miller; Donald E. Baker; Roger E. Bauer; Raymond J. Puigh

doi:dx.doi.org/10.13182/FST89-A39876

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Home / Publications / Journals / Fusion Science and Technology / Volume 15 / Number 2P2B

A Fast Neutron, In Situ Tritium Recovery Experiment on Solid Breeder Materials

G. W. Hollenberg, T. Kurasawa, H. Watanabe, S. E. Berk, I. J. Hastings, J. Miller, Donald E. Baker, Roger E. Bauer, Raymond J. Puigh

Fusion Science and Technology / Volume 15 / Number 2P2B / March 1989 / Pages 1349-1354

Tritium Technology / dx.doi.org/10.13182/FST89-A39876

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An in situ tritium recovery experiment has been designed and is being fabricated for the irradiation of Li₂O in the Fast Flux Test Facility, FFTF. Two in situ tritium recovery canisters will be irradiated with lithium atom burnups to 4%. One canister will provide fundamental data on tritium release as a function of temperature, gas composition, and flow rate. The other canister will contain solid pellet specimens with large (430°C) radial temperature gradients in order to provide integrated performance data.