Development of processes for pilot plant production of purified uranyl nitrate solutions
dc.contributor.author | Alfredson, PG | en_AU |
dc.contributor.author | Charlton, BG | en_AU |
dc.contributor.author | Ryan, RK | en_AU |
dc.contributor.author | Vilkaitis, VK | en_AU |
dc.date.accessioned | 2007-11-22T04:24:34Z | en_AU |
dc.date.accessioned | 2010-04-30T04:36:27Z | en_AU |
dc.date.available | 2007-11-22T04:24:34Z | en_AU |
dc.date.available | 2010-04-30T04:36:27Z | en_AU |
dc.date.issued | 1975-01 | en_AU |
dc.description.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. | en_AU |
dc.identifier.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. | en_AU |
dc.identifier.govdoc | 560 | en_AU |
dc.identifier.isbn | 0642996725 | en_AU |
dc.identifier.other | AAEC-E-344 | en_AU |
dc.identifier.placeofpublication | Lucas Heights, New South Wales | en_AU |
dc.identifier.uri | http://apo.ansto.gov.au/dspace/handle/10238/550 | en_AU |
dc.language.iso | en_au | en_AU |
dc.publisher | Australian Atomic Energy Commission | en_AU |
dc.subject | Uranium dioxide | en_AU |
dc.subject | Solvent extraction | en_AU |
dc.subject | Purification | en_AU |
dc.subject | Uranyl nitrates | en_AU |
dc.subject | Nitric acid | en_AU |
dc.title | Development of processes for pilot plant production of purified uranyl nitrate solutions | en_AU |
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