Publications by Mathieu Hursin

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

Mathieu Hursin, Alessandro Scolaro, 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

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

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

Mathieu Hursin, Alessandro Scolaro, 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