Christophe Demaziere

Editorial - Annals of Nuclear Energy

2024

Open self-paced introductory course in nuclear engineering – How to guarantee student learning

On reactor neutron noise induced by fuel assembly vibrations in large and small heterogenous water-cooled cores

2024

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

GRE@T-PIONEeR: teaching the nuclear data pipeline using innovative pedagogical methods

2023

Education, training and mobility, knowledge management: towards a common effort to ensure a future workforce in Europe and abroad

2023

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

2023

On the simulation of neutron noise induced by vibrations of fuel pins in a fuel assembly

2023

Monitoring and supporting students in their learning – Example of a flipped hybrid course

A three-dimensional two-energy group heterogeneous intrusive Reduced Order Model of xenon oscillations in PWRs

2023

Evolving professional development in nuclear reactor physics and safety through hybrid learning environments

2022

Recommendations for core monitoring to enhance the detection and discrimination of anomalies by neutron noise measurements

2022

Sensitivity analysis in core diagnostics

2022

Understanding the neutron noise induced by fuel assembly vibrations in linear theory

2022

Advanced numerical simulation and modeling for reactor safety - contributions from the CORTEX, McSAFER, and METIS projects

2022

Open source neutron noise modelling

2022

Modelling and simulations of reactor neutron noise induced by mechanical vibrations

On the modelling of fuel assembly vibrations using coarse mesh approaches

Simulations of neutron noise in the research reactor AKR-2: comparison between a discrete ordinates and a diffusion-based method

2022

Verification of the code DYN3D for calculations of neutron flux fluctuations

2022

Development and test of a novel verification scheme applied to the neutronic modelling of Molten Salt Reactors

2022

Uncertainty analyses of neutron noise simulations in a Zero-Power reactor

2022

Active coding assignments in nuclear reactor modelling

Simulations of neutron noise in the research reactor AKR-2: comparison between a discrete ordinates and a diffusion-based method

Understanding xenon oscillations through physics-based Reduced Order Modelling

En hybrid miljö – interaktion, lärarstöd och fördjupat lärande

2022

Machine learning for analysis of real nuclear plant data in the frequency domain

GRE@T-PIONEeR: Teaching computational and experimental reactor physics using innovative pedagogical methods

2021

CORE SIM+: A flexible diffusion-based solver for neutron noise simulations

Comparison of neutron noise solvers based on numerical benchmarks in a 2-D simplified UOX fuel assembly

Scaffolding student learning in computational physics

Development and test of a novel neutronic verification scheme for Molten Salt Reactors

2021

Detection and localisation of multiple in-core perturbations with neutron noise-based self-supervised domain adaptation

Flipping an online module in computational physics

2021

Feature extraction and identification techniques for the alignment of perturbation simulations with power plant measurements

Analysis of the neutron noise induced by fuel assembly vibrations

2021

Combining simulations and machine learning for neutron noise-based core diagnostics

Understanding the neutron noise induced by fuel assembly vibrations in linear theory

2021

On the simulation of neutron noise using a discrete ordinates method

2020

A finite element method for neutron noise analysis in hexagonal reactors

Neutronic Simulation of Fuel Assembly Vibrations in a Nuclear Reactor

Nuclear reactor modeling through distance learning

A time and frequency domain analysis of the effect of vibrating fuel assemblies on the neutron noise

The polarizing effect of the online flipped classroom

2020

Advanced numerical simulation and modelling for reactor safety − contributions from the CORTEX, HPMC, McSAFE and NURESAFE projects

2020

Acceleration of a 2-dimensional, 2-energy group neutron noise solver based on a discrete ordinates method in the frequency domain

The CORTEX project: Improving nuclear fleet operational availability

2020

Monte Carlo-based dynamic calculations of stationary perturbations

2020

Using active learning in hybrid learning environments

2020

Neutron noise-based anomaly classification and localization using machine learning

Using active learning in hybrid learning environments

2020

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

Numerical solution of two-energy-group neutron noise diffusion problems with fine spatial meshes

Modelling of Nuclear Reactor Multi-physics - From Local Balance Equations to Macroscopic Models in Neutronics and Thermal-Hydraulics

Neutron noise simulations in a heterogeneous system: A comparison between a diffusion-based and a discrete ordinates solver

A discrete ordinates solver with diffusion synthetic acceleration for simulations of 2-D and 2-energy group neutron noise problems

PARCS vs CORE SIM neutron noise simulations

2019

Neutron noise modelling for nuclear reactor diagnostics

Development and test of a hybrid probabilistic-deterministic framework based on the interface current method

Neutronic simulation of fuel assembly vibrations in a nuclear reactor

Horizon-2020 ESFR-SMART project on Sodium Fast Reactor Safety: status after 18 months

Assessment of the neutron noise induced by stationary fuel assembly vibrations in a light water reactor

Towards the validation of neutron noise simulators: Qualification of data acquisition systems

Predictive BWR core stability using feedback reactivity coefficients projected on neutronic eigenmodes

Overview of the CORTEX project

Two-level multigrid preconditioning of a neutron noise diffusion solver

Development of a frequency-domain reactor noise simulator based on a neutron transport method

A comparison between time domain and frequency domain calculations of stationary neutron fluctuations

Omvänt klassrum på distans i kärnreaktormodellering

JHR neutron deterministic calculation scheme improvement thanks to Monte Carlo analysis in depletion

Pin-wise homogenization for SP N neutron transport approximation using the finite element method

Does participation affect performance in a flipped online course?

Towards a deep unified framework for nuclear reactor perturbation analysis

Applying SoTL in a nuclear engineering course – experiences from six iterations of course development

JFNK preconditioning for coupled BWR calculations

A deep learning approach to anomaly detection in nuclear reactors

Overview of the CORTEX project

A sensitivity study for reactor neutron noise calculations with a neutron absorber of variable strength

Comparative study of neutron noise calculations using the neutron kinetics code PARCS and the neutron noise simulator CORE SIM

Assessment of criteria for Onset of Flow Instability in vertical narrow rectangular channels with downward flow

QZ-decomposition for matrix-free sweep with high order DG-FEM

Noise-based core monitoring and diagnostics – Overview of the CORTEX project

Uncertainty and sensitivity analysis for the simulation of a station blackout scenario in the Jules Horowitz Reactor

THE NATURE OF INSTABILITIES IN BUBBLY FLOWS/ A COMPARISON BETWEEN EULERIAN-EULERIAN AND EULERIAN-LAGRANGIAN APPROACHES

Setting up a room to cater to online learners’ needs

Schwarz type preconditioners for the neutron diffusion equation

Discontinuity factors for 1D PN equations using a Finite Element Method

Criteria for onset of flow instability in heated vertical narrow rectangular channels at low pressure: an assessment study

2017

Investigation of efficient and reliable numerical algorithms for coupled reactor calculations - XTREAM project - Tasks 3a, 3b and 4a

Development and test of a new verification scheme for transient core simulators

A numerical framework for bubble transport in a subcooled fluid flow

A deterministic against Monte-Carlo depletion calculation benchmark for JHR core configurations

On the dynamics of instabilities in two-fluid models for bubbly flows

Development of a point-kinetic verification scheme for nuclear reactor applications

Core diagnostics using noise analysis: From proof-of-principle to industrial demonstration

Long-term operation of the Swedish Centre for Nuclear Technology (SKC): New challenges and solutions in competence building

Assessment of thermal–hydraulic correlations for narrow rectangular channels with high heat flux and coolant velocity

Estimation of the zero-power reactor transfer from a 3-dimensional core simulator in the frequency domain

Using quizzes and students’ feedback for just-in-time teaching

Investigation of the bias coming from spectrum corrections in the simulations of nucler reactor transients

On the formation of meso-scale structures in dispersed gas-liquid flows

VALIDATION OF HORUS3D/N AGAINST TRIPOLI-4®D FOR CORE DEPLETION CALCULATION OF THE JULES HOROWITZ REACTOR

Use of discontinuity factors in high-order finite element methods

Students' "resonance broadening" to teaching or how to improve students' learning using flipped classrooms

Void reactivity (Cmn) coefficients as indicators of boiling water reactor stability

Comparing Student Activity and Performance in the Classroom and a Virtual Learning Environment

Assessment of Critical Heat Flux correlations in narrow rectangular channels

Homogenization techniques for the neutron transport equation using the finite element method

2015

Coupled fine-mesh neutronics and thermal-hydraulics - modeling and implementation for PWR fuel assemblies

Two-fluid model analyses of instabilities and non-uniformities in bubbly gas-liquid flows

Interior penalty discontinuous Galerkin method for a homogenized diffusion equation in reactor simulations

Substructuring preconditioners for the neutron diffusion equation

Improving teachers-students interactions in web-based courses

A Two-fluid/DQMOM Methodology for Condensation in Bubbly Flow

On the effect of MOX fuel conductivity in predicting melting in FR fresh fuel by means of TRANSURANUS code

The effect of introducing on-line quizzes in a virtual learning environment and implications for the flipped classroom

Numerical investigation of instabilities in the two-fluid model for CFD simulations of LWRs

2015

Instabilities in the two-fluid model relevant to fine-scale simulations of bubbly flows in nuclear reactors

Development of a Monte-Carlo based method for calculating the effect of stationary fluctuations

Using learning analytics in virtual learning environments

Development and test of a transient fine-mesh LWR Multiphysics solver in a CFD Framework

2015

Development of three-dimensional capabilities for modelling stationary fluctuations in nuclear reactor cores

2015

Behaviour and stability of the two-fluid model for fine-scale simulations of bubbly flow in nuclear reactors

Wall superheat prediction in narrow rectangular channels under fully developed boiling of water at low pressures

Modelling of stationary fluctuations in nuclear reactor cores in the frequency domain

Further Development of the Core Simulator CORE SIM: Extension to coupled capabilities for BWRs

Modelling of a self-sustained density wave oscillation and its neutronic response in a three-dimensional heterogeneous system

2014

User's manual of the coupled CORE SIM neutronic and thermo-hydraulic tool

2014

Demonstration of the coupled CORE SIM neutronic and thermo-hydraulic tool

Developing a course in nuclear reactor modelling and going from campus-based to web-based teaching

Reducing axial offset and improving stability in PWRs by using uranium-thorium fuel

Influence of an SN solver in a fine-mesh neutronics/thermal- hydraulics framework

2014

Description of the models and algorithms used in the coupled CORE SIM neutronic and thermo-hydraulic tool

On the prediction of single-phase forced convection heat transfer in narrow rectangular channels

On the validity of the two-fluid model for simulations of bubbly flow in nuclear reactors

Fine-mesh deterministic modeling of PWR fuel assemblies: Proof-of-principle of coupled neutronic/thermal–hydraulic calculations

Students’ and teachers’ perspectives in going from campus-based to web-based teaching

Investigation of the Equilibrium Core Characteristics for the Ringhals-3 PWR with Improved Thermal Margins Using Uranium-thorium Fuel

Multi-physics modelling of nuclear reactors: current practices in a nutshell

INVESTIGATION OF THE POSSIBILITY TO USE A FINE-MESH SOLVER FOR RESOLVING COUPLED NEUTRONICS AND THERMAL-HYDRAULICS

A multi-group neutron noise simulator for fast reactors

Investigation of global and regional BWR instabilities with a four heated-channel Reduced Order Model

Building a comprehensive nuclear education in Sweden

Uncertainty and sensitivity analyses applied to the DRAGONv4.05 code lattice calculations and based on JENDL-4 data

Neutron noise calculations in hexagonal geometry and comparison with analytical solutions

2013

Uncertainty Analyses Applied to the UAM/TMI-1 Lattice Calculations Using the DRAGON (Version 4.05) Code and Based on JENDL-4 and ENDF/B-VII.1 Covariance Data

Validation of PARCS/RELAP5 Coupled codes against a Load Rejection Transient at the Ringhals-3 NPP

Investigation of local BWR instabilities with a four heated-channel Reduced Order Model

On the dependence of the noise amplitude on the correlation length of inlet temperature fluctuations in PWRs

Improvement of LWR thermal margins by introducing thorium

Development of a fully-consistent Reduced Order Model to study instabilities in Boiling Water Reactors

On the possible dependence of the decay ratio on the void reactivity feedback

Statistical uncertainty analisis applied to the DRAGONv4 code lattice calculations and based on JENDL-4 covariance data

Statistical uncertainty analysis applied to the DRAGONv4 code lattice calculations and based on JENDL-4 covariance data

Comments on local power oscillation phenomenon at BWRs

Neutron noise calculations in a hexagonal geometry and comparison with analytical solutions

The Role of Swedish Universities in Supporting SSM Activities in the Field of Deterministic Safety Analysis

2012

Development of a reduced-order model to investigate global/regional/local oscillations in BWRs and study of new stability indicators

Comparison of the calculated neutron noise using finite differences and the Analytical Nodal Method

Comparison of the U.S. NRC PARCS Core Neutronics Simulator Against In-Core Detector Measurements for LWR Applications

Investigation of the MTC noise estimation with a coupled neutronic/thermal-hydraulic dedicated model – “Closing the loop”

A coupled neutronics/thermal–hydraulics tool for calculating fluctuations in Pressurized Water Reactors

Improvement of the thermal margins in the Swedish Ringhals-3 PWR by introducing new fuel assemblies with thorium

Comparison of thorium-based fuels with different fissile components in existing boiling water reactors

Innovative use of Thorium in LWR fuel assemblies

Uncertainty and sensitivity analyses as a validation tool for BWR bundle thermal-hydraulic predictions

Development of a numerical tool for calculating the fluctuations in PWRs

User's manual of the CORE SIM neutronic tool

Validation and demonstration of the CORE SIM neutronic tool

NEUTRON NOISE CALCULATIONS IN THREE-DIMENSIONAL SYSTEMS

Bayesian Uncertainty Analysis of BWR Core Parameters based on Flux Measurements

CORE SIM: A multi-purpose neutronic tool for research and education

Description of the models and algorithms used in the CORE SIM neutronic tool

Neutron noise calculations using the Analytical Nodal Method and comparisons with analytical solutions

Analysis of a loss of normal feedwater transient at the Ringhals-3 NPP using RELAP5/Mod.3.3

Neutron Noise Calculations Using the Analytical Nodal Method

Noise Techniques in Nuclear Systems

Development of a Reduced Order Model and its application to the Forsmark-1 Instability Event of 1996/1997

Statistical uncertainty analyses of void fraction predictions using two different sampling strategies: Latin Hypercube and Random Sampling

Research and Development Program in Reactor Diagnostics and Monitoring with Neutron Noise Methods, Stage 16

Calculation of the neutron noise using the Analytical Nodal Method

Comparative study of 2-group P1 and diffusion theories for the calculation of the neutron noise in 1D 2-region systems

Comparison of thorium-based fuels with different fissile components in existing boiling water reactors

Numerical tools applied to power reactor noise analysis

Method for investigating the applicability of thorium-based fules in existing BWRs

Development of computational methods and their applications for the analysis of nuclear power plants

Comparison of thorium-based fuels with different fissile components in existing BWRs

Comparison of thorium-based fuels with different fissile components in existing boiling water reactors

Multi-fractal analysis of chaotic flashing-induced instabilities in boiling channels in the natural circulation CIRCUS facility

Main steam line break calculations using a coupled relapsiparcs model for the ringhals-3 pressurized water reactor

Calculation of the eigenfunctions of the two-group neutron diffusion equation and application to modal decomposition of BWR instabilities

Analysis of a loss of feedwater case at the Ringhals-3 NPP using RELAP5/PARCS coupled codes

Coupled RELAP5/PARCS main steam line break calculations before and after a power uprate of a Pressurized Water Reactor

Final Report on the Research Project Ringhals Diagnostics and Monitoring, Stage 12

Development and validation of a cross-section interface for PARCS

Main steam line break calculations using a coupled RELAP5/PARCS model for the Ringhals-3 pressurized water reactor

Parametric study of the influence of heterogeneous boron concentration and coolant density on cross section generation in BWRs

Validational exercises with RELAP5/PARCS coupled codes using Ringhals-3 plant data

Development of computational methods and their applications for the analysis of nuclear power plants

Semi-analytical calculations of the neutron noise in 2-group theory for 1-D homogeneous systems

Multi-fractal analysis of chaotic flashing-induced instabilities

Investigation of the validity of the point-kinetic approximation and of the break-frequency method in 2-D subcritical systems

Coupled neutronic/thermal-hydraulic calculations in support to the power uprate of the Ringhals-3 PWR

Calculation of the eigenfunctions and corresponding eigenvalues of the two-group diffusion equation in heterogeneous systems

Development and validation of a coupled PARCS/RELAP5 model of the Ringhals-3 PWR

Investigation of the validity of the point-kinetic approximation and of the break-frequency method in 2-D subcritical systems

Final Report on the Research Project Ringhals Diagnostics and Monitoring Stage 11

Determination of the fuel heat transfer dynamics via CFD for the purpose of noise analysis

Validation of a cross-section interface for PARCS

Development of a coupled PARCS/RELAP5 model of the Ringhals-3 PWR

Development of a cross-section interface for PARCS

Calculation of the Neutron Noise Induced by Shell-Mode Core-Barrel Vibrations in a 1-D, Two-Group, Two-Region Slab Reactor Model

Research and Development Program in Reactor Diagnostics and Monitoring with Neutron Noise Methods, Stage 11 and 12, Final report

Numerical tools applied to power reactor noise analysis

Analysis methods for the determination of possible unseated fuel assemblies in BWRs

Final Report on the Research Project Ringhals Diagnostics and Monitoring, Stage 10

Investigation of the validity of the point-kinetic approximation for subcritical heterogeneous systems in 2-group diffusion theory for measurement of the reactivity in ADS

On the possibility of the space-dependence of the stability indicator (decay ratio) of a BWR

Investigation of the neutron noise induced by shell-mode core-barrel vibrations

Investigation of the frequency-dependence of the MTC noise estimator

Final Report on the Research Project Ringhals Diagnostics and Monitoring, Stage 9

Identification and localization of absorbers of variable strength in nuclear reactors

Research and Development Program in Reactor Diagnostics and Monitoring with Neutron Noise Methods, Stage 10. Final Report

Development of a 2-D 2-group neutron noise simulator

On-line determination of the prompt fraction of in-core neutron detectors in CANDU reactors

Development of a method for measuring the MTC by noise analysis and its experimental verification in Ringhals-2

Development and application of core diagnostics and monitoring for the Ringhals PWRs

Determination of the MTC by noise analysis methods

Study of the MTC estimation by noise analysis in 2-D heterogeneous systems

A phenomenological model for the explanation of a strongly space-dependent Decay Ratio

Analysis of an MTC noise measurement performed in Ringhals-2 using gamma-thermometers and in-core neutron detectors

Final Report on the Research Project Ringhals Diagnostics and Monitoring, Stage 8

Evaluation of the boron dilution method for Moderator Temperature Coefficient measurements

Development of a method for measuring the MTC by noise analysis and its experimental verification in Ringhals-2

Reactor physics calculations on MOX fuel in Boiling Water Reactors (BWRs)

Development of a Noise-Based Method for the Determination of the Moderator Temperature Coefficient of Reactivity (MTC) in Pressurized Water Reactors (PWRs)

Theoretical investigation of the MTC noise estimate in 1-D homogeneous systems

2-D 2-group neutron noise simulator and its application to anomaly localisation

Estimation of the Moderator Temperature Coefficient (Analysis of an MTC measurement using boron dilution method)

Analysis of the reactivity coefficients and the stability of a BWR loaded with MOX fuel

Theoretical investigation of the MTC noise estimate in 1-D homogeneous systems

Theory of neutron noise induced by spatially randomly distributed noise sources