Nuclear wast storage materials

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dc.contributor.authorReeve, KDen_AU
dc.date.accessioned2026-01-16T03:16:31Zen_AU
dc.date.available2026-01-16T03:16:31Zen_AU
dc.date.issued1991en_AU
dc.date.statistics2025-08en_AU
dc.descriptionPhysical copy held by ANSTO Library at DDC 620.1403/1en_AU
dc.description.abstractThis chapter describes different aspects of nuclear waste storage materials. The operation of a nuclear power reactor producing 1300 MW of electrical power typically results in the accumulation of around 30 t of spent fuel per year. The fuel elements are intact but highly radioactive. Leaching tests on sphene glass ceramics containing simulated waste including some with trace-active doping have confirmed their predicted superiority by at least 1–2 orders of magnitude over borosilicate glass. In the associated radiation-damage assessment program, severe radiation damage produced by argon ion bombardment did not increase the leach rate by more than a factor of five. Other glass ceramics that have been studied as nuclear waste forms are celsian glass ceramics, fresnoite glass ceramics, and basalt glass ceramics. The chapter also briefly discusses the following proposals most of which are at an early stage of development: (1) sintered glass, (2) lead-iron-phosphate glasses, (3) high-silica porous glass matrix, (4) multibarrier concepts, and (5) FUETAP. It further highlights borosilicate glass as a generally accepted first-generation form for high-level nuclear waste solidification and storage. Second-generation waste forms designed to increase public acceptability of nuclear waste disposal in the 21st century should have greatly increased leach resistance in ground water. © 1991 Pergamon Press plc. Published by Elsevier Ltd.en_AU
dc.identifier.booktitleConcise Encyclopedia of Advanced Ceramic Materialsen_AU
dc.identifier.citationReeve, K. D. (1991). Nuclear Waste Storage Materials. In R. J. Brook (Ed.), Concise Encyclopedia of Advanced Ceramic Materials (pp. 331-335). Great Britian: Press plc : Pergamon. doi:10.1016/B978-0-08-034720-2.50092-7en_AU
dc.identifier.editorsR. J. Brooken_AU
dc.identifier.isbn0080347207en_AU
dc.identifier.pagination331-335en_AU
dc.identifier.urihttps://apo.ansto.gov.au/handle/10238/16900en_AU
dc.language.isoenen_AU
dc.publisherPergamon Press plcen_AU
dc.relation.urihttps://doi.org/https://doi.org/10.1016/B978-0-08-034720-2.50092-7en_AU
dc.subjectHigh-level radioactive wastesen_AU
dc.subjectRadioactive waste disposalen_AU
dc.subjectWaste storageen_AU
dc.subjectRadioactive waste storageen_AU
dc.subjectSpent fuel storageen_AU
dc.subjectSpent fuelsen_AU
dc.subjectTransuranium compoundsen_AU
dc.subjectNitratesen_AU
dc.subjectUraniumen_AU
dc.subjectPlutoniumen_AU
dc.subjectFast neutronsen_AU
dc.subjectIsotopic exchangeen_AU
dc.subjectFission productsen_AU
dc.subjectBeta-plus decayen_AU
dc.subjectBeta-minus decayen_AU
dc.subjectAmericiumen_AU
dc.titleNuclear wast storage materialsen_AU
dc.typeBook chapteren_AU
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