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|Title: ||Development of processes for pilot plant production of purified uranyl nitrate solutions.|
|Authors: ||Alfredson, PG|
|Keywords: ||Uranium dioxide|
|Issue Date: ||Jan-1975|
|Publisher: ||Australian Atomic Energu 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.|
|Appears in Collections:||Scientific and Technical Reports|
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