Further examination of irradiated hot-pressed beryllium oxide based fuel specimens.

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dc.contributor.authorHanna, GLen_AU
dc.date.accessioned2007-11-22T04:19:28Zen_AU
dc.date.accessioned2010-04-30T04:33:42Zen_AU
dc.date.available2007-11-22T04:19:28Zen_AU
dc.date.available2010-04-30T04:33:42Zen_AU
dc.date.issued1964-08en_AU
dc.description.abstractThe work reported in AAEC/E106 on the metallographic examination of (U,Th)02 dispersed in BeO irradiated in a thermal neutron flux is extended. X—ray diffraction studies have demonstrated that strain developed in the matrixes of both coarse and fine dispersions during irradiation was more severe in the fine dispersion. It is thought that in the coarse dispersion it arose from the swelling of fuel particles and in the fine dispersion, from fission fragment damage. The strain was relieved by annealing in the range 1000 — 1350ºC and was partly relieved in the coarse dispersion by crushing. Fission gas bubbles were observed in the microstructure of specimens annealed at 1250ºC and 1500ºC after irradiation.en_AU
dc.identifier.citationHanna, G. L. (1964). Further examination of irradiated hot-pressed beryllium oxide based fuel specimens. (AAEC/E125). Lucas Heights, NSW: Australian Atomic Energy Commission.en_AU
dc.identifier.govdoc410en_AU
dc.identifier.otherAAEC-E-125en_AU
dc.identifier.urihttp://apo.ansto.gov.au/dspace/handle/10238/331en_AU
dc.language.isoen_auen_AU
dc.publisherAustralian Atomic Energy Commissionen_AU
dc.subjectBeryllium oxidesen_AU
dc.subjectHot pressingen_AU
dc.subjectIrradiationen_AU
dc.subjectFuelsen_AU
dc.subjectThermal neutronsen_AU
dc.subjectX-ray diffractionen_AU
dc.subjectDispersionsen_AU
dc.subjectAnnealingen_AU
dc.titleFurther examination of irradiated hot-pressed beryllium oxide based fuel specimens.en_AU
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