Publications de Mathieu Hursin

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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 ...

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 ...

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 ...

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 ...

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 ...

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 ...

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 ...

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 ...

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 ...

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 ...

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 ...

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 ...

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 ...

This paper presents an assessment conducted at the Paul Scherrer Institut (PSI) of two Monte Carlo-based codes, namely Monteburns and Serpent, for LWR depletion calculations. First, a validation of predicted spent fuel compositions is presented on the basi ...

Mathieu Hursin

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

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

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

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

Bayesian Data Assimilation for Fuel Performance based on OFFBEAT

Treatment of the implicit effect in Shark-X

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

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

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

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

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

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

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

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

Validation of Two Monte Carlo Codes for LWR Burnup Calculations