Two-phase flow across a partially damaged core during the reflood phase of a loca - Université de Lorraine Access content directly
Journal Articles Nuclear Engineering and Design Year : 2013

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.

Dates and versions

hal-01431053 , version 1 (10-01-2017)

Identifiers

Cite

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, 2013, 264, pp.187 - 194. ⟨10.1016/j.nucengdes.2013.02.026⟩. ⟨hal-01431053⟩
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