Open AccessComparison studies of head-end reprocessing using three LWR fuels
Author(s) -
J.H. Goode,
R.G. Stacy,
V.C.A. Vaughen
Publication year - 1980
Language(s) - English
Resource type - Reports
DOI - 10.2172/710833
Subject(s) - plutonium , nuclear fission product , radiochemistry , fission products , uranium dioxide , dissolution , uranium , materials science , zirconium alloy , chemistry , fission , nuclear chemistry , actinide , zirconium , metallurgy , nuclear physics , neutron , physics
The removal of {sup 3}H by voloxidation and the dissolution behavior of two PWR and one BWR fuels were compared in hot-cell studies. The experiments showed that >99% of the {sup 3}H contained in the irradiated UO{sub 2} was volatilized by oxidation in air at 753{sup 0}K (480{sup 0}C). The oxidation did not affect the dissolution of the uranium and plutonium in 7 M HNO{sub 3} (0.02 to 0.03% insoluble plutonium) but did create a fission-product residue that was two to three times more insoluble. From 40 to 69% of the ternary fission-product {sup 3}H was found in the Zircaloy cladding of the fuel rods. Voloxidation had little effect on the {sup 3}H held in the Zircaloy cladding; oxidation for 6 h at 753{sup 0}K released only 0.05% of the {sup 3}H
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