OPAL Reactor: calculation/experiment comparison of neutron flue mapping in fuel coolant channels

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dc.contributor.authorBarbot, Len_AU
dc.contributor.authorDomergue, Cen_AU
dc.contributor.authorVillard, JFen_AU
dc.contributor.authorDestouches, Cen_AU
dc.contributor.authorBraoudakis, Gen_AU
dc.contributor.authorWassink, Den_AU
dc.contributor.authorSinclair, Ben_AU
dc.contributor.authorOsborn, JCen_AU
dc.contributor.authorWu, Hen_AU
dc.date.accessioned2024-04-09T06:37:12Zen_AU
dc.date.available2024-04-09T06:37:12Zen_AU
dc.date.issued2013-10-13en_AU
dc.date.statistics2022-06-09en_AU
dc.description.abstractThe measurement and calculation of the neutron flux mapping of the OPAL research reactor are presented. Following an investigation of fuel coolant channels using sub-miniature fission chambers to measure thermal neutron flux profiles, neutronic calculations were performed. Comparison between calculation and measurement shows very good agreement. © The Authorsen_AU
dc.identifier.citationBarbot, L., Domergue, C., Villard, J.-F., Destouches, C., Braoudakis, G., Wassink, D., Sinclair, B., Osborn, J. C., & Wu, H. (2013). OPAL Reactor: calculation/experiment comparison of neutron flue mapping in fuel coolant channels. Paper presented at the 15th meeting of the International Group on Research Reactors, "IGORR 15", 13-18 Oct 2013, Daejeon, South Korea, Retrieved from: https://www.igorr.com/Documents/2013-DAEJEON/11_1005.pdfen_AU
dc.identifier.conferenceenddate2013-10-18en_AU
dc.identifier.conferencename15th meeting of the International Group on Research Reactors (IGORR 15)en_AU
dc.identifier.conferenceplaceDaejeon, South Koreaen_AU
dc.identifier.conferencestartdate2013-10-13en_AU
dc.identifier.urihttps://www.igorr.com/_media/proceedings:2013_igorr15:11_1005.pdfen_AU
dc.identifier.urihttps://apo.ansto.gov.au/handle/10238/15555en_AU
dc.language.isoenen_AU
dc.publisherInternational Group On Research Reactorsen_AU
dc.relation.urihttps://www.igorr.com/_media/proceedings:2013_igorr15:11_1005.pdfen_AU
dc.subjectComputer calculationsen_AU
dc.subjectCoolantsen_AU
dc.subjectNeutron fluxen_AU
dc.subjectOPAL Reactoren_AU
dc.subjectPool type reactorsen_AU
dc.subjectRadiation fluxen_AU
dc.subjectReactorsen_AU
dc.subjectThermal reactorsen_AU
dc.subjectWater cooled reactorsen_AU
dc.subjectNeutronsen_AU
dc.titleOPAL Reactor: calculation/experiment comparison of neutron flue mapping in fuel coolant channelsen_AU
dc.typeConference Paperen_AU
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