A Fast Neutron, In Situ Tritium Recovery Experiment on Solid Breeder Materials
- 1 March 1989
- journal article
- research article
- Published by Taylor & Francis in Fusion Technology
- Vol. 15 (2P2B) , 1349-1354
- https://doi.org/10.13182/fst89-a39876
Abstract
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.Keywords
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