Two-phase flow across a partially damaged core during the reflood phase of a loca

Abstract : This study focuses on thermal-hydraulic simulations, at sub-channel scale, of a damaged \PWR\ reactor core during a Loss Of Coolant Accident (LOCA). The aim of this study is to simulate the thermal-hydraulics to provide the thermal-mechanical code \DRACCAR\ with an accurate wall heat transfer law. This latter code is developed by the Institut de Radioprotection et de Sûreté Nucléaire (IRSN) to evaluate the thermics and deformations of fuel assemblies within the core. The present paper first describes the use of \CFD\ to perform analysis at sub-channel scale. Then we study the capabilities of existing codes CATHARE-3 and \CESAR\ to simulate dispersed droplet flows.
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Nuclear Engineering and Design, Elsevier, 2013, 264, pp.187 - 194. 〈10.1016/j.nucengdes.2013.02.026〉
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https://hal.univ-lorraine.fr/hal-01431053
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Soumis le : mardi 10 janvier 2017 - 15:13:01
Dernière modification le : lundi 10 septembre 2018 - 13:50:02

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Pierre Ruyer, N. Seiler, B. Biton, F. Lelong, F. Secondi, et al.. Two-phase flow across a partially damaged core during the reflood phase of a loca. Nuclear Engineering and Design, Elsevier, 2013, 264, pp.187 - 194. 〈10.1016/j.nucengdes.2013.02.026〉. 〈hal-01431053〉

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