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Title: Thermal behaviour of the IPR-R1 TRIGA nuclear reactor
Title of periodic: International Journal of Nuclear Science and Technology
Authors: Mesquita, Amir Zacarias
Rezende, Hugo César
Affiliation: Centro de Desenvolvimento da Tecnologia Nuclear/CDTN, Belo Horizonte, MG, Brasil
Centro de Desenvolvimento da Tecnologia Nuclear/CDTN, Belo Horizonte, MG, Brasil
Issue Date: 2007
Keywords: Heat transfer;fuel rods;fuel rods;natural convection;TRIGA-Brazil reactor;subcooled boiling;nucleate boiling;fuel elements
Abstract: Experimental and analytical studies have been performed at the Nuclear Technology Development Center - CDTN (Belo Horizonte) to find out the temperature distribution in the IPR-R1 TRIGA research nuclear reactor, as a function of power and position in the reactor core. The basic safety limit for the TRIGA reactor system is the fuel temperature, both in steady-state and pulsed mode operation. The time dependence of temperature will not be considered here, hence only the steady-state temperature profile will be studied. The experimental results for fuel and coolant temperatures in the reactor core, at different reactor power levels, have been compared with theoretical data and some results from other TRIGA reactors.
Access: L
Appears in Collections:Artigo de periódico

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