On line neutron flux mapping in fuel coolant channels of a research reactor

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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.contributor.authorBlandin, Cen_AU
dc.contributor.authorThévenin, Men_AU
dc.contributor.authorCorre, Gen_AU
dc.contributor.authorNormand, Sen_AU
dc.date.accessioned2024-02-29T03:33:35Zen_AU
dc.date.available2024-02-29T03:33:35Zen_AU
dc.date.issued2014-01-30en_AU
dc.date.statistics2022-06-10en_AU
dc.description.abstractThis work deals with the on-line neutron flux mapping of the OPAL research reactor. A specific irradiation device has been set up to investigate fuel coolant channels using subminiature fission chambers to get thermal neutron flux profiles. Experimental results are compared to first neutronic calculations and show good agreement (C/E ~0.97). © 2022 IEEEen_AU
dc.identifier.booktitle2013 3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA)en_AU
dc.identifier.citationBarbot, L., Domergue, C., Villard, J. F., Destouches, C., Braoudakis, G., Wassink, D., Sinclair, B., Osborn, J. C., Wu, H., Blandin, C., Thévenin, M., Corre, G., & Normand, S. (2013). On line neutron flux mapping in fuel coolant channels of a research reactor. Paper presented at the 2013 3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA), 23-27 June 2013, Marseille, France. In IEEE Transactions on Nuclear Science 62(2). doi:10.1109/ANIMMA.2013.6727951en_AU
dc.identifier.conferenceenddate2013-06-27en_AU
dc.identifier.conferencename2013 3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA)en_AU
dc.identifier.conferenceplaceMarseille, Franceen_AU
dc.identifier.conferencestartdate2013-06-23en_AU
dc.identifier.issn1558-1578en_AU
dc.identifier.uriDOI: 10.1109/ANIMMA31138.2013en_AU
dc.identifier.urihttps://apo.ansto.gov.au/handle/10238/15488en_AU
dc.language.isoenen_AU
dc.publisherIEEEen_AU
dc.subjectOPAL Reactoren_AU
dc.subjectNeutron fluxen_AU
dc.subjectAustralian organizationsen_AU
dc.subjectIrradiationen_AU
dc.subjectCoolantsen_AU
dc.subjectThermal neutronsen_AU
dc.titleOn line neutron flux mapping in fuel coolant channels of a research reactoren_AU
dc.typeConference Paperen_AU
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