Computer analysis of thermal hydraulics for nuclear reactor safety
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Australian Nuclear Association
Abstract
This 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.
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Physical copies held by ANSTO Library at DDC: 621.48/11
Keywords
Boilers, C codes, Calculation methods, Computerized simulation, Cooling systems, Flow models, Fuel elements, H Codes, Heat transfer, HIFAR Reactor, Hydraulics, R codes, Safety analysis, Subcooling, Theoretical data, Transients, Vapor generators, Thermal reactors, Research reactors, Tank Type Reactors
Citation
Tu, 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.