# keywords[]
Networking And Information Technology R&d (nitrd)

# keywords[]
Networking And Information Technology R&d (nitrd)

# keywords[]
4012 Fluid Mechanics And Thermal Engineering

# keywords[]
4019 Resources Engineering And Extractive Metallurgy

# keywords[]
4019 Resources Engineering And Extractive Metallurgy

# keywords[]
4012 Fluid Mechanics And Thermal Engineering

# keywords[]
4019 Resources Engineering And Extractive Metallurgy

# keywords[]
4012 Fluid Mechanics And Thermal Engineering

# keywords[]
3403 Macromolecular And Materials Chemistry

# keywords[]
4019 Resources Engineering And Extractive Metallurgy

# keywords[]
4012 Fluid Mechanics And Thermal Engineering

# keywords[]
70 - Plasma Physics And Fusion Technology

# keywords[]
4019 Resources Engineering And Extractive Metallurgy

# keywords[]
4012 Fluid Mechanics And Thermal Engineering

# keywords[]
4019 Resources Engineering And Extractive Metallurgy

# keywords[]
4012 Fluid Mechanics And Thermal Engineering

# keywords[]
4019 Resources Engineering And Extractive Metallurgy

# keywords[]
4012 Fluid Mechanics And Thermal Engineering

# keywords[]
4019 Resources Engineering And Extractive Metallurgy

# keywords[]
4012 Fluid Mechanics And Thermal Engineering

# keywords[]
4019 Resources Engineering And Extractive Metallurgy

# keywords[]
4012 Fluid Mechanics And Thermal Engineering

# keywords[]
4019 Resources Engineering And Extractive Metallurgy

# keywords[]
4012 Fluid Mechanics And Thermal Engineering

# keywords[]
70 - Plasma Physics And Fusion Technology

# keywords[]
4019 Resources Engineering And Extractive Metallurgy

# keywords[]
4012 Fluid Mechanics And Thermal Engineering

# keywords[]
4019 Resources Engineering And Extractive Metallurgy

# keywords[]
4012 Fluid Mechanics And Thermal Engineering

# keywords[]
4019 Resources Engineering And Extractive Metallurgy

# keywords[]
4012 Fluid Mechanics And Thermal Engineering

# keywords[]
4012 Fluid Mechanics And Thermal Engineering

# keywords[]
4007 Control Engineering, Mechatronics And Robotics

# keywords[]
4012 Fluid Mechanics And Thermal Engineering

# keywords[]
4007 Control Engineering, Mechatronics And Robotics

# keywords[]
3403 Macromolecular And Materials Chemistry

# keywords[]
Machine Learning And Artificial Intelligence

# keywords[]
4019 Resources Engineering And Extractive Metallurgy

# keywords[]
4012 Fluid Mechanics And Thermal Engineering

# keywords[]
4019 Resources Engineering And Extractive Metallurgy

# keywords[]
4012 Fluid Mechanics And Thermal Engineering

# keywords[]
4019 Resources Engineering And Extractive Metallurgy

# keywords[]
4012 Fluid Mechanics And Thermal Engineering

# keywords[]
4019 Resources Engineering And Extractive Metallurgy

# keywords[]
4012 Fluid Mechanics And Thermal Engineering

# keywords[]
4019 Resources Engineering And Extractive Metallurgy

# keywords[]
4012 Fluid Mechanics And Thermal Engineering

# keywords[]
4019 Resources Engineering And Extractive Metallurgy

# keywords[]
4012 Fluid Mechanics And Thermal Engineering

# keywords[]
4019 Resources Engineering And Extractive Metallurgy

# keywords[]
4012 Fluid Mechanics And Thermal Engineering

# publications[].label
Implementation of a Multidimensional Diffusion-Based Neutronics Solver in OFFBEAT

# publications[].label
A Geometric Multiscale modelling approach to the analysis of MSR plant dynamics

# publications[].label
Core SIM+ Simulations of Colibri Fuel Rods Oscillation Experiments and Comparison with Measurements

# publications[].label
An Initiative For The Development And Application Of Open-Source Multi-Physics Simulation In Support Of R&D And E&T In Nuclear Science And Technology

# publications[].label
Towards coupling conventional with high-fidelity fuel behavior analysis tools

# publications[].label
Noise analysis techniques of in-core modulation experiments of the European CORTEX project

# publications[].label
Investigation of Dimensional Effects in the Modeling of Fast-Spectrum MSRs

# publications[].label
Molten Salt Reactor Research in Switzerland

# publications[].label
Development of a semiimplicit contact methodology for finite volume stress solvers

# publications[].label
A reduced order accelerator for time-dependent segregated neutronic solvers

# publications[].label
On the need for multi-dimensional models for the safety analysis of (fast-spectrum) Molten Salt Reactors

# publications[].label
Fuel cycle advantages and dynamics features of liquid fueled MSR

# publications[].label
A Procedure for the Pre-Conceptual Design of Fast Reactors and Application to a Gas-Cooled Sub-Critical Transmuter

# publications[].label
Impact of Thermal Coupling on a Pebblebed Reactor Equilibrium from Hyper-Fidelity Depletion

# publications[].label
Development and verification of the neutron diffusion solver for the GeN-Foam multi-physics platform

# publications[].label
Investigation of Partial Coolant Flow Blockage in a Sodium Fast Reactor Assembly with Coarse-mesh Methodologies

# publications[].label
A coarse-mesh methodology for modelling of single-phase thermal-hydraulics of ESFR innovative assembly design

# publications[].label
Simulation of fission gas release in the 3D fuel performance code OFFBEAT

# publications[].label
Thermo-Hydrodynamics of Internally Heated Molten Salts for Innovative Nuclear Reactors

# publications[].label
Preliminary safety analysis of the TRANSMUTEX sub-critical reactor using the GeN-Foam multi-physics solver

# publications[].label
Creation of an OpenFOAM Fuel Performance Class Based on FRED and Integration Into the GeN-Foam Multi-Physics Code

# publications[].label
Modeling of Sodium Fast Reactors Thermal Expansion Reactivity Feedback Using GeN-Foam and Serpent

# publications[].label
Pre-Release Validation Database for the Multi-Dimensional Fuel Performance Code OFFBEAT

# publications[].label
Detailed modelling of the expansion reactivity feedback in fast reactors using OpenFOAM

# publications[].label
Preliminary Analysis of the MSFR Fuel Cycle Using Modified-EQL3D Procedure

# publications[].label
Thermal-hydraulics of internally heated molten salts and application to the Molten Salt Fast Reactor

# publications[].label
Status and Ongoing Developments for the GeN-Foam Multi-Physics Solver

# publications[].label
NEUTRONIC MODELLING OF THE FFTF CONTROL ROD WORTH MEASUREMENTS WITH DIFFUSION CODES

# publications[].label
Extension of the GeN-Foam neutronic solver to SP3 analysis and application to the CROCUS experimental reactor

# publications[].label
Challenging Common Assumptions of Thick-Wall Chamber Dynamics in Inertial Fusion Systems using MOOSE

# publications[].label
Reduced-Order Modeling of Parameterized Transient Flows in Closed-Lloop Systems

# publications[].label
On the development of multi-physics tools for nuclear reactor analysis based on OpenFOAM: state of the art, lessons learned and perspectives

# publications[].label
Derivation and implementation in OpenFOAM of a point-kinetics model for Molten Salt Reactors

# publications[].label
The GeN-Foam Multiphysics Solver: A Status Update

# publications[].label
Neutron noise experiments in the AKR-2 and CROCUS reactors for the European project CORTEX

# publications[].label
The proto-Earth geo-reactor: Reassessing the hypotheses

# publications[].label
Coupling methodology for the multidimensional fuel performance code offbeat and the Monte Carlo neutron transport code SERPENT

# publications[].label
Reduced-Order Modeling of Parametrized Multi-Physics Computations for the Molten Salt Fast Reactor

# publications[].label
A Time-Dependent Solver for Coupled Neutron-Transport Thermal-Mechanics Calculations and Simulation of a Godiva Prompt-Critical Burst

# publications[].label
Comparison of Reduced-Basis techniques for the model order reduction of parametric incompressible fluid flows

# publications[].label
Bayesian Data Assimilation for Fuel Performance Based on OFFBEAT

# publications[].label
The effectiveness of full actinide recycle as a nuclear waste management strategy when implemented over a limited timeframe  Part I: Uranium fuel cycle

# publications[].label
Data-Driven Reduced-Order Modeling of Convective Heat Transfer in Porous Media

# publications[].label
Development of a novel two-phase flow solver for nuclear reactor analysis: algorithms, verification and implementation in OpenFOAM

# publications[].label
International fuel performance study of fresh fuel experiments for PCMI effects during RIA experiments

# publications[].label
Investigating the Functional Mock-up Interface as a Coupling Framework for the multi-fidelity analysis of nuclear reactors

# publications[].label
Analysis of thorium and uranium fuel cycles in an iso-breeder lead fast reactor using extended-EQL3D procedure

# publications[].label
Dimensional effects in the modelling of MSR dynamics: Moving on from simplified schemes of analysis to a multi-physics modelling approach

# publications[].label
First Steps Towards the Development of a 3D Nuclear Fuel Behavior Solver With OpenFOAM

# publications[].label
Multi-physics modeling of the KIWI-B-4E Nuclear Thermal Propulsion system using OpenMC and GeN-Foam: preliminary assessment against experimental data

# publications[].label
Investigation and Validation of Unstructured Mesh Methodologies for Modeling Experimental Reactors

# publications[].label
Neutronic benchmark of the molten salt fast reactor in the frame of the EVOL and MARS collaborative projects

# publications[].label
A Simplified Numerical Benchmark for Pool-Type Sodium Fast Reactors

# publications[].label
Modeling of Zircaloy Oxidation Through Dynamic Mesh Deformation

# publications[].label
Investigating the Accuracy of Porous-Medium Treatments in the Analysis of Nuclear Thermal Propulsion Systems

# publications[].label
Preliminary development of a coarse-mes h sodium boiling model for openfoam-based multi-physics solvers

# publications[].label
Modelling and analysis of the MSFR transient behaviour

# publications[].label
Application of the OFFBEAT Fuel Performance Code to IAEA Verification Exercises on LMFBR Core Bowing

# publications[].label
Extension of the OFFBEAT fuel performance code to finite strains and validation against LOCA experiments

# publications[].label
Investigation on the effect of eccentricity for fuel disc irradiation tests

# publications[].label
Numerical simulation of compressible fluid-dynamics in the chamber of inertial fusion energy systems

# publications[].label
Thorium breeder and burner fuel cycles in reduced-moderation LWRs compared to fast reactors

# publications[].label
FMI-based multi-fidelity transient analysis of a lead-cooled fast reactor using GeN-Foam and OpenModelica

# publications[].label
The OFFBEAT multi-dimensional fuel behavior solver

# publications[].label
Validation of the GeN-Foam model of the CROCUS experimental reactor

# publications[].label
Paul Scherrer Institutes Studies on Advanced Molten Salt Reactor Fuel Cycle Options

# publications[].label
GeN-ROM-An OpenFOAM(R)-based multiphysics reduced-order modeling framework for the analysis of Molten Salt Reactors

# publications[].label
Preliminary application of the GeN-Foam multiphysics tool to the analysis of the FFTF sodium fast reactor: coupling thermal-hydraulics and core deformations

# publications[].label
The Functional Mock-Up Interface as a Unified Framework to Enable Multi-Scale, Multi-Fidelity and Control-Oriented Simulations of Nuclear Reactors

# publications[].label
A Preliminary Study of the MSFR Dynamics

# publications[].label
Cladding plasticity modeling with the multidimensional fuel performance code OFFBEAT

# publications[].label
Developing Multiphysics, Integrated, High-Fidelity, Massively Parallel Computational Capabilities for Fusion Applications Using MOOSE

# publications[].label
ANALYSIS OF THE FIRST COLIBRI FUEL RODS OSCILLATION CAMPAIGN IN THE CROCUS REACTOR FOR THE EUROPEAN PROJECT CORTEX

# publications[].label
An extended version of the SERPENT-2 code to investigate fuel burn-up and core material evolution of the Molten Salt Fast Reactor

# publications[].label
Full core study of the KIWI-B-4E Nuclear Thermal Propulsion system using OpenMC and GeN-Foam

# publications[].label
FMI-based multi-fidelity and multi-scale simulations of a nuclear reactor

# publications[].label
Reduced-Order Modeling of Fluid Flows in Closed-Loop Systems

# publications[].label
Advanced Modeling and Simulation Methods

# publications[].label
Development and Application of Open-source Modeling and Simulation for Nuclear Reactors

# publications[].label
Multi-Dimensional Creep Analysis Using the Novel Offbeat Fuel Performance Code

# publications[].label
Simulation of Gas Dynamics in the Chamber of Inertial Fusion Energy Systems Using State-of-the-Art Numerical Libraries

# publications[].label
Comparative analysis of thorium and uranium fuel for transuranic recycle in a sodium cooled Fast Reactor

# publications[].label
GEN-FOAM: An OpenFOAM-Based Multi-physics Solver for Nuclear Reactor Analysis

# publications[].label
Analysis of the MSFR Core Neutronics Adopting Different Neutron Transport Models

# publications[].label
A multi-physics time-dependent model for the Lead Fast Reactor single-channel analysis

# publications[].label
Extension of GeN-Foam to modeling of boiling water and validation against the OECD/NRC PSBT benchmark

# publications[].label
Extension of GeN-Foam to departure from nucleate boiling prediction and validation against the OECD/NRC PSBT benchmark

# publications[].label
IAEA Initiative on Open-Source Nuclear Codes for Reactor Analysis

# publications[].label
Development of a novel two-phase flow solver for nuclear reactor analysis: Validation against sodium boiling experiments

# publications[].label
An approach for the modelling and the analysis of the MSR thermo-hydrodynamic behaviour

# publications[].label
Verification of the High Fidelity Model of the CROCUS Experimental Reactor

# publications[].label
Fuel pin behaviour under irradiation with high Pu content: Benchmark exercise

# publications[].label
The effectiveness of full actinide recycle as a nuclear waste management strategy when implemented over a limited timeframe  Part II: Thorium fuel cycle

# publications[].label
Impact of the volume heat source on the RANS-based CFD analysis of Molten Salt Reactors

# publications[].label
CFD-Based Correlation for Forced Convection Heat Transfer in Circular Ducts of Internally Heated Molten Salts

# publications[].label
Impact of Thermal-Hydraulic Feedback and Differential Thermal Expansion on European Sodium-Cooled Fast Reactor Core Power Distribution

# publications[].label
Application of multiphysics model order reduction to doppler/neutronic feedback

# publications[].label
The Proto-Earth Georeactor: A Thorium Reactor?

# publications[].label
Generative AI Tools in the Nuclear Engineering Community: A Survey-Based Evaluation of the Current Adoption and Impacts

# publications[].label
Development in OFFBEAT of a Dynamic-Mesh Incremental Stress-Strain Solver and Validation Against the IFA 650.2 Ballooning Experiment

# publications[].label
IAEAS Coordinated Research Projects on Thermal Hydraulics of Fast Reactors

# publications[].label
Artificial Neural Networks as Surrogate Models for Uncertainty Quantification and Data Assimilation in 2-D/3-D Fuel Performance Studies

# publications[].label
Comparison of Reduced-Basis techniques for the model order reduction of parametric incompressible fluid flows

# publications[].label
The COLIBRI experimental program in the CROCUS reactor: characterization of the fuel rods oscillator

# publications[].label
Preliminary thermal-hydraulics analysis of SFR assembly windows under sodium boiling transients

# publications[].label
Development of a point-kinetics model in OpenFOAM, integration in GeN-Foam, and validation against FFTF experimental data

# publications[].label
GeN-Foam: a novel OpenFOAM based multi-physics solver for 2D/3D transient analysis of nuclear reactors

# publications[].label
Computational study of the Nitrogen-16 source term in the ITER vacuum vessel cooling circuit through the coupling of system-level analysis code and CFD

# publications[].label
Investigation of the MSFR core physics and fuel cycle characteristics

# publications[].label
Preliminary design and analysis of Liquid Fuel Molten Salt Reactor using multi-physics code GeN-Foam

# publications[].label
Development of a High Fidelity Model of the CROCUS Experimental Reactor

# publications[].label
Molten Salt Reactor With Simplified Fuel Recycling and Delayed Carrier Salt Cleaning

# publications[].label
3D Coupled Transient simulation of a fast liquid fuel molten salt reactor primary loop using GeN-Foam