Reprocessing of homogeneous beryllium-based reactor fuel - a suggested scheme for the selective aqueous dissolution of the matrix

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dc.contributor.authorFarrell, MSen_AU
dc.contributor.authorTemple, RBen_AU
dc.date.accessioned2007-11-22T04:29:18Zen_AU
dc.date.accessioned2010-04-30T04:39:22Zen_AU
dc.date.available2007-11-22T04:29:18Zen_AU
dc.date.available2010-04-30T04:39:22Zen_AU
dc.date.issued1962-08en_AU
dc.description.abstractThe matrix of a dilute homogeneous H.T.G.C, reactor fuel employing metallic beryllium as a moderator can be selectively dissolved by a caustic soda solution containing salicylate ion. At least 99 per cent, of the uranium and thorium can be recovered as insoluble solids, but in the case of irradiated material the uranium loss might be higher. Some decontamination of the resulting beryllium solution from fission products and Pa233 can also be obtained. A tentative chemical flowsheet is proposed on the basis of the results obtained.en_AU
dc.identifier.citationFarrell, M. S., Temple, R. B. (1962). The reprocessing of homogeneous beryllium-based reactor fuel. a suggested scheme for the selective aqueous dissolution of the matrix (AAEC/E93). Lucas Heights, NSW: Research Establishment, Australian Atomic Energy Commission.en_AU
dc.identifier.govdoc738en_AU
dc.identifier.otherAAEC-E-93en_AU
dc.identifier.urihttp://apo.ansto.gov.au/dspace/handle/10238/728en_AU
dc.language.isoen_auen_AU
dc.publisherAustralian Atomic Energy Commissionen_AU
dc.subjectReprocessingen_AU
dc.subjectDissolutionen_AU
dc.subjectAqueous solutionsen_AU
dc.subjectNuclear fuelsen_AU
dc.subjectBerylliumen_AU
dc.subjectMatricesen_AU
dc.titleReprocessing of homogeneous beryllium-based reactor fuel - a suggested scheme for the selective aqueous dissolution of the matrixen_AU
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