Transient analysis in the 3D nodal kinetics and thermal-hydraulics ANDES/COBRA coupled system

Lozano Montero, Juan Andrés; Aragonés Beltrán, José María y García Herranz, Nuria (2008). Transient analysis in the 3D nodal kinetics and thermal-hydraulics ANDES/COBRA coupled system. En: "International Conference on the Physics of Reactors “Nuclear Power: A Sustainable Resource”", 14/09/2008-18/09/2008, Interlaken, Suiza. ISBN 978-3-9521409-5-6. pp. 1-8.

Descripción

Título: Transient analysis in the 3D nodal kinetics and thermal-hydraulics ANDES/COBRA coupled system
Autor/es:
  • Lozano Montero, Juan Andrés
  • Aragonés Beltrán, José María
  • García Herranz, Nuria
Tipo de Documento: Ponencia en Congreso o Jornada (Artículo)
Título del Evento: International Conference on the Physics of Reactors “Nuclear Power: A Sustainable Resource”
Fechas del Evento: 14/09/2008-18/09/2008
Lugar del Evento: Interlaken, Suiza
Título del Libro: Book of Abstracts
Fecha: 14 Junio 2008
ISBN: 978-3-9521409-5-6
Volumen: 2
Materias:
Escuela: E.T.S.I. Industriales (UPM)
Departamento: Ingeniería Nuclear [hasta 2014]
Licencias Creative Commons: Reconocimiento - Sin obra derivada - No comercial

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Resumen

Neutron kinetics has been implemented in the 3D nodal solver ANDES, which has been coupled to the core thermal-hydraulics (TH) code COBRA-III for core transient analysis. The purpose of this work is, first, to discuss and test the ability of the kinetics solver ANDES to model transients; and second, by means of a systematic analysis, including alternate kinetics schemes, time step size, nodal size, neutron energy groups and spectrum, to serve as a basis for the development of more accurate and efficient neutronics/thermal-hydraulics tools for general transient simulations. The PWR MOX/UO2 transient benchmark provided by the OECD/NEA and US NRC was selected for these goals. The obtained ANDES/COBRA-III results were consistent with other solutions to the benchmark; the differences in the TH feedback led to slight differences in the core power evolution, whereas very good agreements were found in the other requested parameters. The performed systematic analysis highlighted the optimum kinetics iterative scheme, and showed that neutronics spatial discretization effects have stronger influence than time discretization effects, in the semi-implicit scheme adopted, on the numerical solution. On the other hand, the number of energy groups has an important influence on the transient evolution, whereas the assumption of using the prompt neutron spectrum for delayed neutrons is acceptable as it leads to small relative errors.

Más información

ID de Registro: 3351
Identificador DC: http://oa.upm.es/3351/
Identificador OAI: oai:oa.upm.es:3351
Depositado por: Memoria Investigacion
Depositado el: 15 Jun 2010 11:03
Ultima Modificación: 20 Abr 2016 12:54
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