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Title: Development of processes for pilot plant production of purified uranyl nitrate solutions
Authors: Alfredson, PG
Charlton, BG
Ryan, RK
Vilkaitis, VK
Keywords: Uranium dioxide
Solvent extraction
Uranyl nitrates
Nitric acid
Issue Date: Jan-1975
Publisher: Australian Atomic Energy Commission
Citation: Alfredson, P. (1975). Development of processes for pilot plant production of purified uranyl nitrate solutions (AAEC/E344). Lucas Heights, N.S.W.: Australian Atomic Energy Commission, Research Establishment.
Abstract: Nuclear purity uranyl nitrate solutions were produced from Rum Jungle yellow cake by dissolution in nitric acid and purification by solvent extraction with 20 vol.% tributyl phosphate in kerosene using pump -mix mixer-settler contactors. The design of the equipment, experimental studies and operating experience are described. Dissolution of yellow cake and recycled uranium oxide materials was readily carried out in a 100 ℓ dissolver to give solutions containing 300 gU ℓ -1 and 0.5 to 4 П nitric acid. Filtration of silica from this solution prior to solvent extraction was not necessary in this work for yellow cake containing 0.25 per cent silica. A low acid flowsheet for uranium purification was developed in which the nitric acid consumption was reduced by 76 per cent and the throughput of the mixer-settler units was increased by 67 per cent compared with the initial design flowsheet. Nine extraction and seven scrubbing stages were used with a feed solution containing 300 gU ℓ -1 and 1.0 П nitric acid and with a portion of the product recycled as scrub solution. The loaded organic phase was stripped in 16 stages with 0.05 П nitric acid heated to 60º C to give a 120 gU ℓ -1 product. The uranium concentration in the raffinate was < 0.04 g ℓ-1, corresponding to ~ 0.01 per cent of the feed.
Gov't Doc #: 560
ISBN: 0642996725
Appears in Collections:Scientific and Technical Reports

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