Axel Laureau

A coupled compressible multiphase thermohydraulic–neutronics solver for simulating rapid reactivity insertions in molten salt reactors

Anna Maitre, Nathalie Marie, Frédèric Bertrand, Axel Laureau et autres

A Coupled Compressible Multiphase Thermohydraulic–Neutronics Solver for Simulating Rapid Reactivity Insertions in Molten Salt Reactors

Anna Maitre, Nathalie Seiler, Frédéric Bertrand, Axel Laureau et autres

Study of the Beta Spectrum Shape of Rb 92 and Cs 142 Decays for the Prediction of Reactor Antineutrino Spectra

G. A. Alcalá, Alejandro Algora, M. Estienne, M. Fallot et autres

The shapes of the beta spectra of ^{92}Rb and ^{142}Cs, two of the beta decays most relevant for the prediction of the antineutrino spectrum in reactors, have been measured. A new setup composed of two ΔE-E telescopes has been used. High-purity radioactive …

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Study of beta spectrum shapes relevant to the prediction of reactor antineutrino spectra

German Alcala, Alejandro Algora, M. Estienne, M. Fallot et autres

International audience

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β Decay Spectra Measurements for the Study of Reactors’ Antineutrino Spectra

G. A. Alcalá, Alejandro Algora, M. Fallot, M. Estienne et autres

Updated reactor antineutrino spectra predictions, based on the Huber-Muller Conversion model, revealed discrepancies known as the Reactor Antineutrino Anomaly (RAA) and the spectral “bump”, raising concerns about the accuracy of the models and data used for these predictions. Consequently, improved nuclear data …

es, hu, fr, pl, gb, fi (code pays fourni par la source)

Exploring the safety and performance of molten salt reactors for their deployment in the European Union: the MIMOSA and ENDURANCE projects

Isabelle Morlaes, Stefano Lorenzi, Sophie Deanesi, Anna L. Smith et autres

Molten Salt Reactors (MSR) are Generation IV nuclear systems in which the fuel is dissolved in a molten salt circulating through the primary system. There is growing interest in this advanced technology in Europe, but also in the US, China, South Korea, …

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Modeling of fuel salt compressibility in MSR using blastFOAM, reference and accelerated calculations using transfer function

Thibault Le Meute, Axel Laureau, Franco Moretti, E. Merle et autres

This article presents the work performed to compute the impact of compressibility on the fuel salt of Molten Salt Reactors (MSRs) on reactivity density feedback evolution in the OpenFOAM solver, blastFoam. Reactivity density feedback is a crucial aspect of the chain reaction …

New model developments for fuel supply strategies in molten salt reactors: Application to the REM depletion code

Louiliam Clot, E. Merle, Axel Laureau, Daniel Heuer et autres

In recent years, a particular family of molten salt reactors (MSRs) – those designed to burn plutonium and minor actinides – has attracted considerable interest from research institutions and companies, including CNRS and Orano. NRS/LPSC Grenoble has been studying and optimising MSRs …

fr (code pays fourni par la source)

Pile-oscillation results for stainless steel with local and 3D global measurements

Thomas Ligonnet, Axel Laureau, Oskari Pakari, Daniel Clément et autres

The BLOOM pile-oscillation program on stainless steel and minor alloying elements was successfully conducted in the CROCUS reactor at EPFL between fall 2024 and spring 2025. For this purpose, a pile-oscillator and a new instrumented channel capable of measuring thermal neutrons as …

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CORTEX experiments – Part I: Modulation campaigns in AKR-2 & CROCUS for the validation of neutron noise codes

Vincent Pierre Lamirand, Alexander Knospe, Klemen Ambrožič, Sebastian Hübner et autres

ch, de, si, se, fr (code pays fourni par la source)

CORTEX experiments, Part II: Postprocessing of neutron noise time series to determine reliable mean and uncertainties

Klemen Ambrožič, Alexander Knospe, Oskari Pakari, Sebastian Hübner et autres

si, ch, de (code pays fourni par la source)

Tool Developments in the OpenMC Code: Correlated Sampling and Transient Fission Matrix Approach Coupled to OpenFOAM

Axel Laureau, Thibault Le Meute, Thomas Ligonnet, E. Merle

This article outlines the advancements made in broadening the application scope of the OpenMC neutron transport code to include thermohydraulic coupling and nuclear data uncertainty propagation. These developments primarily involve the incorporation of the correlated sampling (CS) technique, facilitating the propagation of …

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