Publications de Carlo Fiorina | EPFL Graph Search

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In this study, a hypothetical fast spectrum Liquid Fuel Molten Salt Reactor (LFMSR) core is modeled using the multiphysics C++ code GeN-Foam (General Nuclear Foam). GeN-Foam is based on OpenFOAM, a C++ opensource library for solution of continuum mechanics ...

The GeN-Foam multi-physics code enables coupled thermal-hydraulic, neutronic, and thermal-mechanical analysis of fast reactor cores with 3-D unstructured deformable meshes. Advances within the Horizon2020 ESFR-SMART project, as well as trends towards highe ...

This work presents a projection-based multiphysics Model Order Reduction (MOR) framework for the analysis of nuclear systems and its application to parametric simulations of Molten Salt Reactors (MSR). The framework, named GeN-ROM, is developed using OpenF ...

A porous medium-based representation of nuclear reactors and complex engineering systems more in general can significantly reduce simulation and modelling costs, while preserving a reasonable degree of accuracy via regime map-based correlations for modelli ...

The OpenFOAM Fuel BEhavior Analysis Tool, or OFFBEAT, is a multi-dimensional fuel performance code under collaborative development at the Laboratory for Reactor Physics and Systems Behaviour (LRS) of the EPFL and at the PSI. The code can be used both for s ...

In the last two decades, the use of OpenFOAM as a multi-physics library for nuclear applications has grown from a sporadic use for exploratory studies to a widespread application for the analysis of innovative reactor concepts and highly complex problems. ...

The deterministic solution of the neutron transport problem entails the coupled solution of several partial differential equations, one for each energy group, direction and/or spherical harmonic. Several techniques have been devised for accelerating the so ...

Heat transfer phenomena involving internally heated fluid flows are of particular interest in several industrial applications, in chemical plants as in the nuclear field. This topic is relevant for the development of the Molten Salt Reactors (MSRs) since i ...

The applicability of two Reduced-Basis techniques to parametric laminar and turbulent incompressible fluid flow problems in nuclear engineering is studied in this work. The Reduced-Basis methods are used to generate Reduced-Order Models (ROMs) that can acc ...

The mechanical analysis of nuclear fuel behavior under base-irradiation conditions has traditionally been performed adopting the small-strain approximation. However, many cases of interest for fuel behavior involve the occurrence of large rod deformations ...

This work presents a data-driven Reduced-Order Model (ROM) for parametric convective heat transfer problems in porous media. The intrusive Proper Orthogonal Decomposition aided Reduced-Basis (POD-RB) technique is employed to reduce the porous medium formul ...

This paper preliminarily investigates the use of data-driven surrogates for fuel performance codes. The objective is to develop fast-running models that can be used in the frame of uncertainty quantification and data assimilation studies. In particular, da ...

Following the growing interest that we observe in the use of OpenFOAM for nuclear reactor analysis, the current work presents a point-kinetics model and associated open-source code that can easily be inte-grated in existing thermal-hydraulic solvers to str ...

The present article gives an overview of the first experimental campaigns carried out in the AKR-2 and CROCUS reactors within the framework of the Horizon 2020 European project CORTEX. CORTEX aims at developing innovative core monitoring techniques that al ...

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 ...

This paper presents the results of the first phase of the benchmark exercise in the PuMMA project, aimed at extending the reliability of fuel performance codes for Mixed Oxide (MOX) fuels with high plutonium content. The exercise involved the simulation of ...

Several efforts have been spent in recent years to address the simulation challenges posed by the non-conventional design of Molten Salt Reactors (MSRs). One of the design specificities of MSRs is the volume heat source in the liquid fuel, which has been p ...

Recent numerical advancements at the Laboratory for Reactor Physics and Systems Behaviour (LRS) have led to the development of a novel two-phase porous medium-based thermal-hydraulic simulation tool, integrated in the broader multi-physics framework of the ...

The current work presents a simplified benchmark for a pool-type Sodium Fast Reactor based on a 2D (r-z) geometry for testing tightly-coupled spatial neutron transport, thermal-hydraulics and thermal-mechanics modeling. The new benchmark is motivated by de ...

In this paper, a proper orthogonal decomposition based reduced-order model is presented for parametrized multiphysics computations. Our application physics is Doppler feedback in a simplified model of the molten salt fast reactor concept. The reduced model ...

Carlo Fiorina

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Preliminary design and analysis of Liquid Fuel Molten Salt Reactor using multi-physics code GeN-Foam

A coarse-mesh methodology for modelling of single-phase thermal-hydraulics of ESFR innovative assembly design

GeN-ROM-An OpenFOAM(R)-based multiphysics reduced-order modeling framework for the analysis of Molten Salt Reactors

Development of a novel two-phase flow solver for nuclear reactor analysis: algorithms, verification and implementation in OpenFOAM

The OFFBEAT multi-dimensional fuel behavior solver

On the development of multi-physics tools for nuclear reactor analysis based on OpenFOAM (R): state of the art, lessons learned and perspectives

A reduced order accelerator for time-dependent segregated neutronic solvers

Cfd-Based Correlation For Forced Convection Heat Transfer In Circular Ducts Of Internally Heated Molten Salts

Comparison of Reduced-Basis techniques for the model order reduction of parametric incompressible fluid flows

Extension of the OFFBEAT fuel performance code to finite strains and validation against LOCA experiments

Data-Driven Reduced-Order Modeling of Convective Heat Transfer in Porous Media

Artificial Neural Networks as Surrogate Models for Uncertainty Quantification and Data Assimilation in 2-D/3-D Fuel Performance Studies

Development of a point-kinetics model in OpenFOAM, integration in GeN-Foam, and validation against FFTF experimental data

Neutron noise experiments in the AKR-2 and CROCUS reactors for the European project CORTEX

Investigation and Validation of Unstructured Mesh Methodologies for Modeling Experimental Reactors

PuMMA blind benchmark: Performance of high plutonium content MOX fuel under irradiation

Impact of the volume heat source on the RANS-based CFD analysis of Molten Salt Reactors

Development of a novel two-phase flow solver for nuclear reactor analysis: Validation against sodium boiling experiments

A Simplified Numerical Benchmark For Pool-Type Sodium Fast Reactors

Application of multiphysics model order reduction to doppler/neutronic feedback