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Aurélia Chenu

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Related publications (8)

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Aurélia Chenu

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A wrapper tube for a fuel subassembly of a nuclear reactor core and method for protecting fuel against overheating in case of coolant boiling

Coupled 3-D Neutronics/Thermal-Hydraulics Optimization Study For Improving The Response Of A 3600 Mw(Thermal) Sfr Core To An Unprotected Loss-Of-Flow Accident

Analysis of selected Phenix EOL tests with the FAST code system - Part I: Control-rod-shift experiments

Analysis of selected Phenix EOL tests with the FAST code system - Part II: Unprotected phase of the Natural Convection Test

Single- and Two-Phase Flow Modeling for Coupled Neutronics/Thermal-Hydraulics Transient Analysis of Advanced Sodium-Cooled Fast Reactors

Pressure drop modeling and comparisons with experiments for single- and two-phase sodium flow

FAST code system: Review of recent developments and near-future plans

TRACE simulation of sodium boiling in pin bundle experiments under loss-of-flow conditions