The irradiation behaviour of beryllium based dispersion fuels - a preliminary irradiation experiment.

Simple item page
dc.contributor.authorHanna, GLen_AU
dc.contributor.authorHickman, BSen_AU
dc.contributor.authorHilditch, RJen_AU
dc.date.accessioned2007-11-22T04:29:20Zen_AU
dc.date.accessioned2010-04-30T04:39:24Zen_AU
dc.date.available2007-11-22T04:29:20Zen_AU
dc.date.available2010-04-30T04:39:24Zen_AU
dc.date.issued1962-09en_AU
dc.description.abstractThe effects of fission fragment damage on vacuum hot pressed fuel specimens of (U Th) Be13 dispersed in a beryllium matrix were examined by irradiation in a predominantly thermal neutron flux. Damage equivalent to that caused by 4 x 10 19 to 11 x 10 19 fissions per cm3 (depending on specimen composition) was achieved at temperatures between 435º and 530ºC. All specimens increased in volume on irradiation. The increases ranged from 0.1 per cent, to 5 per cent., depending on the volume fraction of fuel phase and the number of fissions per cm3. Some of the volume change — possibly up to 0.7 per cent. — was due to thermal effects alone. Release of fission gases was as high as 2 per cent, in some cases and was generally higher than would be expected from recoil in specimens having no open porosity. The fractional release was greater in specimens which experienced a high volume increase. Microstructures showed no significant change on irradiation. All specimens were slightly porous before irradiation and it is considered that the swelling of specimens was due to the growth of existing pores and that the release of fission gases was facilitated by an increase in open porosity.en_AU
dc.identifier.citationHanna, G. L., Hickman, B. S. & Hilditch, R. J. (1962). The irradiation behaviour of beryllium based dispersion fuels - a preliminary irradiation experiment. (AAEC/E96). Lucas Heights, NSW: Australian Atomic Energy Commission.en_AU
dc.identifier.govdoc740en_AU
dc.identifier.otherAAEC-E-96en_AU
dc.identifier.urihttp://apo.ansto.gov.au/dspace/handle/10238/730en_AU
dc.language.isoen_auen_AU
dc.publisherAustralian Atomic Energy Commissionen_AU
dc.subjectBerylliumen_AU
dc.subjectIrradiationen_AU
dc.subjectFuelsen_AU
dc.subjectDispersionsen_AU
dc.subjectHot pressingen_AU
dc.titleThe irradiation behaviour of beryllium based dispersion fuels - a preliminary irradiation experiment.en_AU
Files
Original bundle
Now showing 1 - 1 of 1
Thumbnail Image
Name:
AAEC-E-96.pdf
Size:
1.45 MB
Format:
Adobe Portable Document Format
Description:
Download
Collections
Scientific and Technical Reports