Integral modelling for nuclear spent fuel Dry storage systems using computational fluid Dynamics

Hernandez-Avellaneda, Andres; Varas, Gonzalo Jiménez; Benavides, Julio; Rey, Luis; Martinez-Murillo, Juan Carlos

doi:10.1016/j.anucene.2021.108851

Cited by 6 publications

(2 citation statements)

References 15 publications

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“…Esta metodología, desarrollada en colaboración con Centrales Nucleares Almaraz y Trillo (CNAT), ha sido aplicada en trabajos fin de grado y fin de master (Benavides, 2016(Benavides, , 2015, tesis (Benavides, 2021), ponencias de congreso (Hernandez-Avellaneda et al, 2021 y artículos científicos (Benavides et al, 2019;Hernandez-Avellaneda et al, 2022).…”

Section: Metodologíaunclassified

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Metodología para el desarrollo de modelos de contenedores de combustible nuclear gastado mediante el código Ansys CFX

Avellaneda¹

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The management of spent fuel has always been one of the challenges in the nuclear power operation and generation. In some of the nuclear power plants in operation, the available space in the spent fuel pool it is reaching the limit, therefore spent fuel needs to be stored using dry storage options.As a frequent dry storage option, the nuclear spent fuel casks can be highlighted. Numerous nuclear power plants both in the world and in Spain already have independent spent fuel storage installations, where the spent fuel casks are stored. These installations are considered absolutely necessary both for the continuity of the nuclear power plants once they have reached their spent fuel pool capacity, and during the decommissioning phase.

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Section: Metodologíaunclassified

“…Sin embargo, aún no se ha verificado la importancia de la radiación térmica dentro del propio contenedor. Este estudio, junto con el modelo Integral base, se encuentra publicado en el artículo (Hernandez-Avellaneda et al, 2022).…”

Section: Sensibilidad Ante La Radiación En El Modelo Integralunclassified

Metodología para el desarrollo de modelos de contenedores de combustible nuclear gastado mediante el código Ansys CFX

Avellaneda¹

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Modelling fuel assembly flow nozzles in a spent nuclear fuel dry cask using CFD codes

Hernandez-Avellaneda¹,

Varas²,

Rey³

et al. 2023

Annals of Nuclear Energy

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Comparative thermo-hydraulic study of different nuclear spent fuel cask designs using CFD codes

Hernandez-Avellaneda

Varas

Rey

et al. 2023

Annals of Nuclear Energy

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Integral modelling for nuclear spent fuel Dry storage systems using computational fluid Dynamics

Cited by 6 publications

References 15 publications

Metodología para el desarrollo de modelos de contenedores de combustible nuclear gastado mediante el código Ansys CFX

Metodología para el desarrollo de modelos de contenedores de combustible nuclear gastado mediante el código Ansys CFX

Modelling fuel assembly flow nozzles in a spent nuclear fuel dry cask using CFD codes

Comparative thermo-hydraulic study of different nuclear spent fuel cask designs using CFD codes

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