Gas-cooled reactors of a mixed fuel-moderator type

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dc.contributor.authorDalton, GCJen_AU
dc.date.accessioned2024-05-29T06:49:59Zen_AU
dc.date.available2024-05-29T06:49:59Zen_AU
dc.date.issued1958-06-02en_AU
dc.date.statistics2024-05-23en_AU
dc.descriptionPhysical copies held by ANSTO Library at DDC: 539.7/348en_AU
dc.description.abstractReactors of this type may use any of the moderators, graphite, beryllium oxide or beryllium, and one of the coolant gases hydrogen, helium, carbon dioxide, nitrogen or other suitable gas to be selected on the grounds of compatibility with the moderator and circuit materials and engineering suitability. The uranium233-thorium fuel cycle is the most suitable because the conversion factor possible with this system is greater than with the Z plutonium-uranium238 cycle. Because there is no necessity for lumping the fuel, the moderator may be used to dilute the fuel and to increase the surface available for heat transfer to the coolant. This dilution should also improve the burn-up possible before the 6 fuel element suffers physical disintegration. The fuel and fertile material may be mixed uniformly with the moderator, or may be in a thin, enriched layer near the surface of the element. The fuel elements may be rods, spheres, plates, or bricks, pierced by coolant channels. Research will be directed towards the production of a high integrity fuel element, the solution of problems of compatibility of gas and moderator, control of fission products and reprocessing and refabricating fuel elements. It is expected that this type of reactor will have particular application in the power range of 5 to 5OMW.en_AU
dc.identifier.booktitleAustralian Atomic Energy Symposium, 1958 : proceedings of a Symposium on the Peaceful Uses of Atomic Energy in Australia held in Sydney from June 2 to 6, 1958en_AU
dc.identifier.citationDalton, G. C. J. (1958). Gas-cooled reactors of a mixed fuel-moderator type. Paper present to the Australian Atomic Energy Symposium, 1958, "Peaceful Uses of Atomic Energy In Australia, Sydney, June 2 to 6, 1958. In Australian Atomic Energy Symposium, 1958 : proceedings of a Symposium on the Peaceful Uses of Atomic Energy in Australia held in Sydney from June 2 to 6, 1958. Carlton, Victoria : Melbourne University Press on behalf of the Australian Atomic Energy Commission, (pp. 340-345).en_AU
dc.identifier.conferenceenddate1958-06-06en_AU
dc.identifier.conferencenameAustralian Atomic Energy Symposium, 1958, Symposium on the Peaceful Uses of Atomic Energy in Australiaen_AU
dc.identifier.conferenceplaceSydney, Australiaen_AU
dc.identifier.conferencestartdate1958-06-02en_AU
dc.identifier.pagination340-345en_AU
dc.identifier.placeofpublicationCarlton, Victoriaen_AU
dc.identifier.urihttps://apo.ansto.gov.au/handle/10238/15617en_AU
dc.language.isoenen_AU
dc.publisherMelbourne University Press on behalf of The Australian Atomic Energy Commissionen_AU
dc.subjectReactorsen_AU
dc.subjectGas cooled reactorsen_AU
dc.subjectReactor fuelingen_AU
dc.subjectGraphiteen_AU
dc.subjectBeryllium oxidesen_AU
dc.subjectBerylliumen_AU
dc.subjectHydrogenen_AU
dc.subjectHeliumen_AU
dc.subjectCarbon dioxideen_AU
dc.subjectNitrogenen_AU
dc.subjectUranium 233en_AU
dc.titleGas-cooled reactors of a mixed fuel-moderator typeen_AU
dc.typeConference Paperen_AU
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