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Mathieu Hursin

Cette personne a quitté l’EPFL

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Publications associées (65)

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Modeling, verification and validation of multiple PWR depletion cycles with DRAGON and PARCS

Benjamin Meunier, Mathieu Hursin

This paper introduces a methodology for modeling Pressurized Water Reactors (PWRs) across multiple depletion cycles using the DRAGON and PARCS codes. The approach incorporates history effects to improve the accuracy of reactor simulations, specifically foc ...

2025

Convergence Analysis and Criterion for Data Assimilation with Sensitivities from Monte Carlo Neutron Transport Codes

Andreas Pautz, Mathieu Hursin, Daniel Jerôme Siefman

Sensitivity coefficients calculated with Monte Carlo neutron transport codes are subject to statistical fluctuations. The fluctuations affect parameters that are calculated with the sensitivity coefficients. The convergence study presented here describes t ...

ANS2018

Analysis of diffusion coefficient correction methods applied for small-core, high-leakage reactors

Mathieu Hursin

Nodal diffusion codes have been successfully used for decades as a primary tool of commercial power reactor design, safety calculations and plant cycle simulations. The large-size, small-leakage property of these reactor cores and the appropriately generat ...

2022

Neutronics modeling of the CROCUS reactor with SERPENT and PARCS codes

Andreas Pautz, Mathieu Hursin, Daniel Jerôme Siefman, Adolfo Rais

This paper reports the methodology used for the neutronic modelling of the CROCUS reactor and discusses the challenges encountered during the process. Full-core steady-state neutronics solutions were computed with the PARCS code. The Serpent Monte Carlo co ...

2017

On data assimilation with Monte-Carlo-calculated and statistically uncertain sensitivity coefficients

Andreas Pautz, Mathieu Hursin, Daniel Jerôme Siefman

Sensitivity coefficients from Monte Carlo neutron transport codes have uncertainties that can affect nuclear data adjustments with integral experiments. This paper presents an extended version of Generalized Linear Least Squares (GLLS), called xGLLS, that ...

PERGAMON-ELSEVIER SCIENCE LTD2020

Uncertainty quantification of Cl-35 nuclear data on a Molten Chloride Fast Reactor

Mathieu Hursin

This study investigates the impact of 35Cl nuclear data uncertainties on the neutronics of Molten Chloride Fast Reactors (MCFR), specifically focusing on two models: MCFR-C and MCFR-D. Using the Monte Carlo code SERPENT2, a comprehensive sensitivity analys ...

2025

Case Study of Data Assimilation Methods with the LWR-Proteus Phase II Experimental Campaign

Andreas Pautz, Mathieu Hursin, Daniel Jerôme Siefman

This paper describes the application of data assimilation methods to CASMO-5 simulations of a Proteus research reactor experiment. Its focus is a comparison and evaluation of three prominent data assimilation methods: generalized linear least squares, MOCA ...

2017

Enhancing higher education through hybrid and flipped learning: Experiences from the GRE@T-PIONEeR project

Yi Zhang, Mathieu Hursin

GRE@T-PIONEeR is a Horizon 2020 project coordinated by Chalmers University of Technology, running over the period 2020-2024. 18 university teachers from 8 different universities located in 6 different countries gathered forces to develop and offer advanced ...

Elsevier Science Sa2024

Intercomparison of neutron noise measurement systems in the CROCUS reactor

Andreas Pautz, Mathieu Hursin, Vincent Pierre Lamirand, Oskari Ville Pakari

In the framework of an international collaboration, the critical decay constant (α0 = β/Λ), and delayed neutron fraction (β) of the CROCUS reactor were measured by teams of EPFL/PSI, CEA and SCK•CEN research institutes using the Rossi-α and Power Spectral ...

American Nuclear Society2018

Verification of a reactor physics calculation scheme for the CROCUS reactor

Andreas Pautz, Mathieu Hursin, Daniel Jerôme Siefman, Adolfo Rais, Gaëtan Girardin

CROCUS is a zero power (100 W) reactor of the Laboratory for Reactor Physics and Systems Behavior (LRS) at the Swiss Federal Institute of Technology, Lausanne (EPFL). It is used for teaching and research purposes. Its modeling has relied so far on diffusio ...

2014

Comparison of Bayesian Model Calibration Techniques for Future Application to Fuel Performance Behavior Models

Mathieu Hursin, Alessandro Scolaro, Sara Maccario

This paper explores data assimilation methods in the context of Bayesian Calibration for fuel performance models. It compares deterministic and stochastic approaches, concentrating on the Generalized Linear Least Squares (GLLS) method and stochastic techni ...

American Nuclear Society2024

Synergies in Vver Reactor Long-term Operation and Aging: a Comprehensive Review of Camivver, Delisa-lto, and Everest Projects

Mathieu Hursin

This paper reviews the synergies between three Euratom projects-CAMIVVER, DELISA-LTO, and EVEREST-focusing on the long-term operation (LTO) and safety assessment of VVER reactors. These projects address challenges associated with extending the lifespan of ...

EDP SCIENCES S A2025

OECD-NEA EXPERT GROUP ON REACTOR SYSTEMS MULTI-PHYSICS: DEVELOPMENT OF VERIFICATION AND VALIDATION GUIDELINES FOR MULTI-PHYSICS SIMULATIONS

Mathieu Hursin

Over the past decades, national and multi-national efforts have been established to develop high-fidelity, multi-physics, and multi-scale modeling and simulation (M&S) tools for design and safety challenges for existing and advanced reactors. These tools a ...

American Society of Mechanical Engineers (ASME)2024

Bayesian Data Assimilation for Fuel Performance based on OFFBEAT

Andreas Pautz, Mathieu Hursin, Alessandro Scolaro, Carlo Fiorina

The EPFL and the PSI have been developing in recent years a new fuel performance tool named OFFBEAT. The tool is based on the OpenFOAM finite-volume library and allows for 1.5-D, 2-D and 3-D fuel performance analyses, both for base irradiation and for tran ...

American Nuclear Society2022

CORE SIM+ simulations of COLIBRI fuel rods oscillation experiments and comparison with measurements

Andreas Pautz, Vincent Pierre Lamirand, Mathieu Hursin, Carlo Fiorina, Oskari Ville Pakari, Pavel Frajtag, Axel Guy Marie Laureau, Adolfo Rais, Daniel Godat, Paolo Vinai

At EPFL, the CROCUS reactor has been used to carry out experiments with vibrating fuel rods. The paper presents a first attempt to employ the measured data to validate CORE SIM+, a neutron noise solver developed at Chalmers University of Technology. For th ...

2021

Treatment of the implicit effect in Shark-X

Mathieu Hursin, Hakim Ferroukhi

Shark-X is a set of Perl-based tools build around the deterministic neutron transport code CASMO-5, used to perform uncertainty quantification for lattice calculations at the Paul Scherrer Institut (PSI). While perturbing an input parameter, e.g. a cross s ...

2020

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

Andreas Pautz, Vincent Pierre Lamirand, Mathieu Hursin, Oskari Ville Pakari, Pavel Frajtag, Axel Guy Marie Laureau, Fanny Vitullo, Adolfo Rais, Thomas Jean-François Ligonnet, Nicolas Weiss, Daniel Godat, Klemen Ambrozic

We present the experimental campaigns – namely, three per facility – carried out between 2018 and 2021 in the AKR–2 and CROCUS zero power reactors within the framework of the Horizon 2020 European project CORTEX. Their purpose was to produce high-quality a ...

2025

Steady-state neutronic measurements and comprehensive numerical analysis for the BME training reactor

Mathieu Hursin

This paper describes steady-state reactor physics measurements and calculations that were performed for the Training Reactor of Budapest University of Technology and Economics (BME TR) with the purpose of benchmarking. Based on the available geometry speci ...

2021

Improved Evaluated Nuclear Data in the Resonance Region by Combining Energy Dependent Measurements and Depletion Calculations: Application to Pu-239+n, Pu-240+n and Pu-241+n

Mathieu Hursin

The determination of resonance parameters for neutron interactions with material is a complex process. In most cases it is very difficult to de termine an ac curate es timate of th e fu ll se t of parameters from an analysis of energy dependent cross secti ...

American Nuclear Society2024

Methods and Models for the Coupled Neutronics and Thermal-Hydraulics Analysis of the CROCUS Reactor at EFPL

Andreas Pautz, Mathieu Hursin, Daniel Jerôme Siefman, Adolfo Rais, Gaëtan Girardin

In order to analyze the steady state and transient behavior of the CROCUS reactor, several methods and models need to be developed in the areas of reactor physics, thermal-hydraulics, and multiphysics coupling. The long-term objectives of this project are ...

2015