Mechanisms of radiation damage and properties of nuclear materials

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dc.contributor.authorLumpkin, GRen_AU
dc.contributor.authorSmith, KLen_AU
dc.contributor.authorWhittle, KRen_AU
dc.contributor.authorThomas, BSen_AU
dc.contributor.authorMarks, NAen_AU
dc.date.accessioned2011-01-21T02:21:52Zen_AU
dc.date.available2011-01-21T02:21:52Zen_AU
dc.date.issued2009-11-30en_AU
dc.date.statistics2009-11-30en_AU
dc.description.abstractA wide range of materials are currently under consideration for use in advanced nuclear fuel cycle applications. The effects of radiation on these materials by exposure to external neutron irradiation and internal alpha and beta decay processes may have significant effects on the physical and chemical properties. This is especially true for materials that are subject to hundreds of displacements per atom during their service life. In this paper, we explore some of the radiation damage mechanisms prevalent in oxide based materials, including mathematical models and other concepts of amorphization (e.g., percolation), the role of defects on picosecond time scales, and longer term effects such as diffusion and recrystallization. As radiation "tolerance" or the ability of a material to maintain crystallinity under intense irradiation is a key issue for many fuel cycle applications, we will briefly review and comment on some of the underlying factors that have been identified as important in driving the short-term damage recovery. These include aspects of the structure (e.g., connectivity, polyhedral distortion), bonding, energetics of defect formation and migration, and melting point and similar criteria. The primary materials of interest here are those under development as special purpose nuclear waste forms, novel materials for separations, inert matrix fuels, and transmutation targets. In this context, we will illustrate the behavior of simple oxides and several more complex oxides such as perovskite, multicomponent fluorite systems, and related derivative structures (e.g., pyrochlore and zirconolite). The damage mechanisms in these materials are briefly compared with those of intermetallic and metallic materials.en_AU
dc.description.sponsorshipAdvanced Diamond Technologies; AGD; Apollo Diamond; Applied Diamond Incorporated; CEA LIST Instituteen_AU
dc.identifier.booktitleMaterials Research Society Symposium Proceedingsen_AU
dc.identifier.citationLumpkin, G. R., Smith, K. L., Whittle, K. R., Thomas, B. S., & Marks, N. A. (2009). Mechanisms of radiation damage and properties of nuclear materials. Paper presented to the 2009 MRS Fall Meeting - "Materials Research Needs to Advance Nuclear Energy (Symposium V)", 30th November – 4th December 2009. Boston, Massachusetts, United States of America: Hynes Convention Center. In Materials Research Society Symposium Proceedings, 1215, 19-26. Warrendale, Pennsylvania, United States of America: Materials Research Society.en_AU
dc.identifier.conferenceenddate4 December 2009en_AU
dc.identifier.conferencename2009 MRS Fall Meeting - 'Materials Research Needs to Advance Nuclear Energy (Symposium V)en_AU
dc.identifier.conferenceplaceBoston, Massachusettsen_AU
dc.identifier.conferencestartdate30 November 2009en_AU
dc.identifier.govdoc3146en_AU
dc.identifier.isbn9781605111889en_AU
dc.identifier.issn0272-9172en_AU
dc.identifier.issue19-26en_AU
dc.identifier.placeofpublicationWarrendale, Pennsylvaniaen_AU
dc.identifier.urihttp://apo.ansto.gov.au/dspace/handle/10238/2945en_AU
dc.identifier.urihttp://dx.doi.org/10.1557/PROC-1215-V04-01en_AU
dc.identifier.volume1215en_AU
dc.language.isoenen_AU
dc.publisherMaterials Research Societyen_AU
dc.subjectCeramicsen_AU
dc.subjectRadioactive wastesen_AU
dc.subjectRadiation effectsen_AU
dc.subjectTransmutationen_AU
dc.subjectIrradiationen_AU
dc.subjectDefectsen_AU
dc.titleMechanisms of radiation damage and properties of nuclear materialsen_AU
dc.typeConference Presentationen_AU
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