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

G. W. HollenbergPacific NW Laboratory P.O. Box 999 Richland, WA 99352 (509) 376-5515

T. KurasawaJapan Atomic Energy Research Institute Tokai-mura, Naka-gun, Ibaraki 319-11, Japan 292-82-5403

H. WatanabeJapan Atomic Energy Research Institute Tokai-mura, Naka-gun, Ibaraki 319-11, Japan 292-82-5403

S. E. BerkU.S. D.O.E./OFE Washington, DC 20545 (301) 353-4171

I. J. HastingsAtomic Energy of Canada Research Company Chalk River Nuclear Lab. Chalk River, Ontario Canada K0J1J0 (613) 584-3311

J. MillerAtomic Energy of Canada Research Company Chalk River Nuclear Lab. Chalk River, Ontario Canada K0J1J0 (613) 584-3311

Donald E. BakerWestinghouse Hanford Co. P.O. Box 1970 Richland, WA 99352 (509) 376-3766

Roger E. BauerWestinghouse Hanford Co. P.O. Box 1970 Richland, WA 99352 (509) 376-3766

Raymond J. PuighWestinghouse Hanford Co. P.O. Box 1970 Richland, WA 99352 (509) 376-3766

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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.

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

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

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