The irradiation behaviour of cold-pressed and sintered beryllium oxide dispersion fuels.

dc.contributor.authorHanna, GLen_AU
dc.contributor.authorHilditch, RJen_AU
dc.date.accessioned2007-11-22T04:10:05Zen_AU
dc.date.accessioned2010-04-30T04:31:20Zen_AU
dc.date.available2007-11-22T04:10:05Zen_AU
dc.date.available2010-04-30T04:31:20Zen_AU
dc.date.issued1964-06en_AU
dc.description.abstractCoarse and fine dispersions of (U.Th)O2 in BeO, prepared by cold-pressing and sintering, were exposed to fission fragment damage by irradiation in a thermalised neutron flux. Irradiation temperatures were between 610ºC and 720ºC and fission densities of 3 x 1019 to 2 x 1020 fissions per cm3 of compact were achieved. The dimensional stability of all specimens was very good and the greatest volume expansion was one per cent. Estimated thermal stresses ranged up to 32,000 p.s.i. but no thermal stress failure occurred. The fine and the most dilute coarse dispersions released only 0.1 per cent, of the fission gases but the remaining coarse dispersions released from 0.6 to 4.9 per cent. Coarse fuel particles were generally cracked after irradiation and by microscopy, fission fragment damage to the fuel — BeO interfaces was observed in the high burn—up specimens. Fission gas bubbles developed in coarse fuel particles on post—irradiation annealing at 1250ºC and 1500ºC.en_AU
dc.identifier.citationHanna. G. L., & Hilditch, R. J. (1964). The irradiation behaviour of cold-pressed and sintered beryllium oxide dispersion fuels. (AAEC/E124). Lucas Heights, NSW: Australian Atomic Energy Commission.en_AU
dc.identifier.govdoc274en_AU
dc.identifier.otherAAEC-E-124en_AU
dc.identifier.urihttp://apo.ansto.gov.au/dspace/handle/10238/74en_AU
dc.language.isoen_auen_AU
dc.publisherAustralian Atomic Energy Commissionen_AU
dc.subjectBeryllium oxidesen_AU
dc.subjectIrradiationen_AU
dc.subjectDispersionsen_AU
dc.subjectFuelsen_AU
dc.subjectCold pressingen_AU
dc.titleThe irradiation behaviour of cold-pressed and sintered beryllium oxide dispersion fuels.en_AU
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