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Computer analysis of thermal hydraulics for nuclear reactor safety

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dc.contributor.authorTu, TYen_AU
dc.contributor.authorYeoh, GHen_AU
dc.contributor.authorStorr, GJen_AU
dc.contributor.authorBeattie, DRHen_AU
dc.date.accessioned2026-02-05T00:52:17Zen_AU
dc.date.issued2001-10-23en_AU
dc.date.statistics2025-01-15en_AU
dc.descriptionPhysical copies held by ANSTO Library at DDC: 621.48/11en_AU
dc.description.abstractThis paper gives an overview of ANSTO's capability and recent research and development activities in thermal hydraulic modelling for nuclear reactor safety analysis, particularly for our research reactor, HIFAR (High Flux Australian Reactor) and its intended replacement, the Replacement Research Reactor (RRR). Several tools contribute to ANSTO's capability in thermal hydraulic modelling, including RELAP (developed in US) - a code for reactor system thermal-hydraulic analysis; CFS (developed in UK) - a general computational fluid dynamics code , which was used for thermal hydraulic analysis in reactor fuel elements; and HIZAPP (developed at ANSTO) - for coupling neutronics with thermal-hydraulics for reactor transient analysis.en_AU
dc.identifier.booktitleANA 2001: Fourth Conference on Nuclear Science & Engineering in Australia : the Millenium Hotel, Kings Cross, NSW, Australia, 24-25 October 2001 : Conference Handbooken_AU
dc.identifier.citationTu, J., Yeoh, G., Storr, G., & Beattie. D. (2001). Computer analysis of thermal hydraulics for nuclear reactor safety. Paper presented to the Fourth Conference on Nuclear Science & Engineering in Australia, Kings Cross, NSW, Australia, 24-25 October 2001. In ANA 2001: Fourth Conference on Nuclear Science & Engineering in Australia: the Millennium Hotel, Kings Cross, NSW, Australia, 24-25 October 2001: Conference Handbook (pp. 150-155). Canberra, ACT: Australian Nuclear Association. The Association.en_AU
dc.identifier.conferenceenddate2001-10-25en_AU
dc.identifier.conferencenameANA 2001: Fourth Conference on Nuclear Science & Engineering in Australiaen_AU
dc.identifier.conferenceplaceKings Cross, New South Walesen_AU
dc.identifier.conferencestartdate2001-10-24en_AU
dc.identifier.govdoc0949188131en_AU
dc.identifier.pagination150-155en_AU
dc.identifier.placeofpublicationCanberra, ACTen_AU
dc.identifier.urihttps://apo.ansto.gov.au/handle/10238/17001en_AU
dc.language.isoenen_AU
dc.publisherAustralian Nuclear Associationen_AU
dc.subjectBoilersen_AU
dc.subjectC codesen_AU
dc.subjectCalculation methodsen_AU
dc.subjectComputerized simulationen_AU
dc.subjectCooling systemsen_AU
dc.subjectFlow modelsen_AU
dc.subjectFuel elementsen_AU
dc.subjectH Codesen_AU
dc.subjectHeat transferen_AU
dc.subjectHIFAR Reactoren_AU
dc.subjectHydraulicsen_AU
dc.subjectR codesen_AU
dc.subjectSafety analysisen_AU
dc.subjectSubcoolingen_AU
dc.subjectTheoretical dataen_AU
dc.subjectTransientsen_AU
dc.subjectVapor generatorsen_AU
dc.subjectThermal reactorsen_AU
dc.subjectResearch reactorsen_AU
dc.subjectTank Type Reactorsen_AU
dc.titleComputer analysis of thermal hydraulics for nuclear reactor safetyen_AU
dc.typeConference Paperen_AU

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