Heat transfer in homogeneous gas-cooled reactors

Simple item page
dc.contributor.authorde Vahl Davis, Gen_AU
dc.date.accessioned2024-06-04T06:39:37Zen_AU
dc.date.available2024-06-04T06:39:37Zen_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.abstractThe heat source distribution in a nuclear reactor is a function of neutron flux, fuel loading, and core temperature, each of which is a function of position. In certain types of solid fuel gas-cooled reactors, the fuel distribution is such that the reactor may be regarded as homogeneous. This paper describes the method of calculating the temperature distribution in the core of such a reactor. A cyclindrical core is assumed, and the variations of coolants flow and outlet temperature with radius are found. As a first approximation the dependence of neutron flux on temperature is taken to be small and the flux is assumed to have been calculated on the basis of uniform core temperature. using this flux distribution, the first core temperature distribution is found. Subsequent flux distributions can be calculated to refine the values of temperatures.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.citationde Vahl Davism G. (1958). Heat transfer in homogeneous gas-cooled reactors. 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. 471-474).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.pagination471-474en_AU
dc.identifier.placeofpublicationCarlton, Victoriaen_AU
dc.identifier.urihttps://apo.ansto.gov.au/handle/10238/15625en_AU
dc.language.isoenen_AU
dc.publisherMelbourne University Press on behalf of The Australian Atomic Energy Commissionen_AU
dc.subjectHeat transferen_AU
dc.subjectGas cooled reactorsen_AU
dc.subjectNeutron fluxen_AU
dc.subjectTemperature rangeen_AU
dc.subjectCalculation methodsen_AU
dc.subjectHomogeneous reactorsen_AU
dc.titleHeat transfer in homogeneous gas-cooled reactorsen_AU
dc.typeConference Paperen_AU
Files
Original bundle
Now showing 1 - 1 of 1
Thumbnail Image
Name:
Vahl Davis.pdf
Size:
422.37 KB
Format:
Adobe Portable Document Format
Description:
Download
License bundle
Now showing 1 - 1 of 1
Thumbnail Image
Name:
license.txt
Size:
1.63 KB
Format:
Item-specific license agreed upon to submission
Description:
Download
Collections
Conference Publications