Publications de Mathieu Hursin

Preliminary Sensitivity Analysis of Time-Dependent Code Outputs in Fuel Performance Models Using OFFBEAT for Future Calibration

Alessandro Scolaro, Mathieu Hursin, Edoardo Luciano Brunetto

Fuel performance codes are essential for predicting fuel rod behavior in nuclear reactors. These codes comprise a complex system of models with empirical constants that require calibration against experimental data. To support this calibration, this study ...

American Nuclear Society2025

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

Assessment of JEFF Nuclear Data Libraries for Reactor Physics and Spent Fuel Composition Applications

Mathieu Hursin

Informa UK Limited2025

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

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

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

Measurement of the Prompt Neutron Decay Constant in a Zero-Power Reactor Using a Novel 3D Detector System

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

Analyzing neutron noise in zero-power reactors provides information about integral parameters, such as the prompt decay constant

\alpha

alpha. This information can be used to validate codes that predict said parameters, or time-dependent behavior, part ...

TAYLOR & FRANCIS INC2025

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

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

Verification of the nTRACER/CTF code system for full core high resolution cycle analysis with the OECD/NEA TVA Watts Bar Unit 1 benchmark

Mathieu Hursin, Marianna Papadionysiou

This study aims to develop and verify the multi-physics high-resolution coupled code system nTRACER/CTF for full core depletion calculations in Cartesian geometry. The verifications are conducted on the basis of the OECD/NEA TVA Watts Bar 1 benchmark (TVA ...

2025

Comparison of high-fidelity transport code predictions against the NECTAR intra-pin reaction rate measurements

Andreas Pautz, Oskari Ville Pakari, Vincent Pierre Lamirand, Mathieu Hursin, Thomas Jean-François Ligonnet, Tom Mager

The advancement of high-fidelity nuclear reactor simulation methods is essential for reducing conservatism in safety margins and optimizing reactor design and operation. This work evaluates the predictive capabilities of the deterministic solvers GeN-Foam ...

2025

In-Memory, Fully-Parallel Coupling of GeN-Foam and OFFBEAT: Towards a New Milestone in High-Fidelity, Finite-Volume Nuclear Reactor Simulation

Alessandro Scolaro, Mathieu Hursin, Thomas Arthur Louis Joseph Guilbaud

The design and safety analysis of advanced fuel materials and innovative Gen-IV reactor concepts, with their distinct physical and engineering requirements compared to conventional reactors, has often been the main drive behind the development of modern mu ...

American Nuclear Society2025

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

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

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

Alessandro Scolaro, Mathieu Hursin

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

Preliminary Validation of Intra-pin Reaction Rate Predictions from the Deterministic Transport Codes GeN-Foam and MPACT

Andreas Pautz, Mathieu Hursin, Tom Mager

In response to the scarcity of validation benchmarks for high-fidelity neutronics solvers predicting pin-resolved neutron flux distributions, the Laboratory for Reactor Physics and Systems Behaviour (LRS) at the Swiss Federal Institute of Technology Lausan ...

American Nuclear Society2024

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

Andreas Pautz, Adolfo Rais, Oskari Ville Pakari, Vincent Pierre Lamirand, Mathieu Hursin, Axel Guy Marie Laureau

In this paper we present the methodology developed to analyze the detector response of neutron noise experiments performed at EPFL CROCUS and TUD AKR-2 reactors in the framework of the H2020 CORTEX project. The noise, or modulation, is induced by controlle ...

2024

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

Application of the PSI cycle check-up methodology for full-core Monte Carlo simulations verified using pin power estimates and validated for hot zero power conditions

Mathieu Hursin

Monte Carlo (MC) based neutron transport codes provide high-fidelity numerical solutions to problems beyond the modelling capabilities of conventional core simulation methods. However, performing core-follow calculations with MC codes remains challenging d ...

PERGAMON-ELSEVIER SCIENCE LTD2024

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

Mathieu Hursin, Yi Zhang

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

Intra-pin Reaction Rate Measurements in the CROCUS Experimental Reactor

Andreas Pautz, Oskari Ville Pakari, Vincent Pierre Lamirand, Mathieu Hursin, Thomas Jean-François Ligonnet, Tom Mager

In response to the need for validating high-fidelity deterministic neutronics solvers capable of providing pin-resolved neutron flux distributions, intra-pin reaction rates measurements were performed in the CROCUS experimental reactor. A specially designe ...

2024

Computation of sensitivity coefficients in fixed source simulations with SERPENT2

Andreas Pautz, Mathieu Hursin

Within the scope of the implementation of a nuclear data pipeline aiming at producing the best possible evaluated nuclear data files, a major point is the production of relevant sensitivity coefficients when including integral benchmark information. Thanks ...

Elsevier Science Sa2024

Modeling of Sodium Fast Reactors Thermal Expansion Reactivity Feedback using GeN-Foam and Serpent

Alessandro Scolaro, Mathieu Hursin

Sodium-cooled fast reactors (SFRs) offer a promising alternative to conventional light-water technologies but present unique safety and design challenges. Among others, reactivity feedback effects associated to core deformations are significantly larger th ...

American Nuclear Society2024