Mathieu Hursin

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Publications associées (65)

Analysis of transient measurements with thermal feedback and coupled TRACE/PARCS calculations performed on the BME Training Reactor

Mathieu Hursin

This paper presents nuclear reactor transient measurements with thermal feedback and corresponding coupled neutronic-thermohydraulic simulations performed for the natural circulation cooled Training Reactor of Budapest University of Technology and Economic ...

2023

Design of an Instrumented Fuel Rod for Intra-pin Neutron Flux Measurements in the CROCUS Experimental Reactor

Andreas Pautz, Vincent Pierre Lamirand, Mathieu Hursin, Thomas Jean-François Ligonnet, Won Dong Shin, Tom Mager

In response to the need for validating high-fidelity deterministic neutronics solvers capable of pin-resolved neutron flux distributions, an instrumented fuel rod was designed for the experimental reactor CROCUS, operated by EPFL’s Laboratory for Reactor P ...

2023

Monte Carlo analysis of BWR geometries using a cycle check-up methodology

Mathieu Hursin, Hakim Ferroukhi, Dimitri Rochman, Abdelhamid Dokhane, Alexander Vasiliev

Recent fuel anomalies at a Swiss power plant have motivated the development at PSI of the "Cycle Check-Up" (CHUP) methodology which consists in performing Monte Carlo transport calculations using nuclide compositions and thermal-hydraulic boundary conditio ...

Pergamon-Elsevier Science Ltd2023

Thermal-hydraulic measurements and TRACE system code analysis performed on the natural circulation cooled BME Training Reactor

Mathieu Hursin

This paper presents a validation exercise for a natural circulation cooled, light-water moderated and cooled pool-type reactor system. Measurements were performed in the 100 kW Training Reactor of the Budapest University of Technology and Economics, which ...

2023

Modeling noise experiments performed at AKR-2 and CROCUS zero-power reactors

Vincent Pierre Lamirand, Mathieu Hursin

CORTEX is a EU H2020 project (2017-2021) devoted to the analysis of 'reactor neutron noise' in nuclear reactors, i.e. the small fluctuations occurring around the stationary state due to external or internal disturbances in the core. One important aspect of ...

2023

Investigation and Validation of Unstructured Mesh Methodologies for Modeling Experimental Reactors

Andreas Pautz, Mathieu Hursin, Carlo Fiorina, Tom Mager

This paper summarizes a methodology developed at Ecole Polytechnique Federale de Lausanne for the neutronic modeling of the CROCUS experimental reactor and proposes solutions to the challenges one may face while modeling a research reactor with a complex g ...

MDPI2022

Iterative Bayesian Monte Carlo for nuclear data evaluation

Mathieu Hursin

In this work, we explore the use of an iterative Bayesian Monte Carlo (iBMC) method for nuclear data evaluation within a TALYS Evaluated Nuclear Data Library (TENDL) framework. The goal is to probe the model and parameter space of the TALYS code system to ...

2022

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

Bayesian Data Assimilation for Fuel Performance based on OFFBEAT

Andreas Pautz, Mathieu Hursin, Carlo Fiorina, Alessandro Scolaro

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

Sensitivity analysis in core diagnostics

Mathieu Hursin

In the CORTEX project, methods to simulate neutron flux oscillations were enhanced and machine-learning based tools to determine the causes of measured neutron flux oscillations were developed, using the results of simulations as training and validation da ...

2022

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Thermal-hydraulic measurements and TRACE system code analysis performed on the natural circulation cooled BME Training Reactor

Mathieu Hursin

2023

Analysis of transient measurements with thermal feedback and coupled TRACE/PARCS calculations performed on the BME Training Reactor

Mathieu Hursin

2023

Modeling noise experiments performed at AKR-2 and CROCUS zero-power reactors

Vincent Pierre Lamirand, Mathieu Hursin

2023