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BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
Yu-Keung Sze, Joseph Alfred Gosselin
Nuclear Technology | Volume 63 | Number 3 | December 1983 | Pages 431-441
Technical Paper | Chemical Processing | doi.org/10.13182/NT83-A33270
Articles are hosted by Taylor and Francis Online.
A systematic method has been used to screen a number of potential stabilizers (holding reductants) for Pu(III) in tri-n-butyl phosphate/diluent solutions used in irradiated fuel reprocessing systems. The conditions assumed were similar to those used in solvent extraction contactor operations. Of the reagents tested, oximes as a group appeared to be very effective. Acetaldoxime, in particular, was selected for extensive tests and was used as a Pu(III) stabilizer, in both the aqueous and organic phases, in contactor runs for plutonium partition from thorium and uranium. In the best results, the plutonium loss to the thorium/uranium stream was 2.8 × 10−5 g/ℓ or 0.0046%; without using acetaldoxime, the loss was 12%. Rates of plutonium reduction in 1.5 M nitric acid have been compared for a number of reducing agents under identical conditions. Some derivatives of hydroxylamine were found to be much more effective than hydroxylamine itself.