Publications by Alessandro Scolaro

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Fuel performance codes are an essential tool for ensuring the safe and economic opera-tion of nuclear reactors. Traditionally, these codes have been developed following a simple 1.5-D modelling approach, where the fuel behavior is simplified by assuming ax ...

This paper presents the results of High-burnup Experiments for Reactivity-initiated Accident (HERA) Modeling & Simulation (M&S) exercise. The HERA project under the Nuclear Energy Agency (NEA) Second Framework for Irradiation Experiments (FIDES-II) program ...

The design and safety analysis of advanced fuel materials and innovative Gen-IV reactor concepts, with their distinct physical and engineering requirements compared to conventional reactors, has often been the main drive behind the development of modern mu ...

Hydrogen generated during the waterside corrosion of zirconium claddings can diffuse within the material, forming hydrides that alter the mechanical properties of the claddings. These hydrides may lead to detrimental effects such as delayed hydride crackin ...

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 ...

Sodium-cooled fast reactors (SFRs) offer a promising alternative to conventional light-water technologies but present unique safety and design challenges. Among others, reactivity feedback effects associated to core deformations are significantly larger th ...

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 ...

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 ...

The recently developed Multi-Physics Pellet Cladding Mechanical Interaction Validation (MPCMIV) benchmark includes dedicated transient fuel performance exercises. In this work, three fuel performance codes (BISON, OFFBEAT, FAST) are used to perform support ...

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 ...

Fuel performance codes are essential for predicting fuel rod behavior in nuclear reactors. These codes comprise a complex system of models with empirical constants that require calibration against experimental data. To support this calibration, this study ...

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 ...

In this work, we propose a modelling approach for the intra-granular fission gas behaviour in UO2 under restructuring process. Leveraging the definition of restructured volume fraction, we consider the fuel matrix transition from the non-restructured to th ...

Porous-medium thermal-hydraulic modeling has become more popular in recent years for reactor analysis due to its flexibility and the ease of its implementation within multi-physics, PDE-oriented libraries like OpenFOAM and MOOSE.A porous-medium approach of ...

This paper presents simulations of Reactivity Initiated Accident on PWR fuel rods performed with two fuel performance codes: ALCYONE and OFFBEAT. These simulations were carried out in the framework of the first phase of the High-Burnup Experiments of React ...

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 ...

The compact design of microreactors can potentially lead to a strong interdependence between neutronics and thermo-mechanics, making the development of coupling methodologies essential to quantify the importance of such effects. This study introduces a hig ...

The OpenFOAM Fuel Behaviour Analysis Tool (OFFBEAT), developed jointly by EPFL and PSI in Switzerland, is rapidly gaining recognition as a comprehensive code for multi-dimensional thermo-mechanical fuel behaviour analysis. Like for any novel code, verifica ...

The past decades have seen numerous efforts to apply the finite volume methodology to solid mechanics problems. However, only limited work has been done by the finite volume community toward the simulation of mechanical contact. In this article, we present ...

Generative AI tools (often abbreviated genAI or GAI), such as chatGPT, have arguably great potential to induce a paradigm shift in knowledge work.Herein, we present the results of a survey conducted within the nuclear engineering professional community to ...

Alessandro Scolaro

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Development of a Novel Finite Volume Methodology for Multi-Dimensional Fuel Performance Applications

International fuel performance study of fresh fuel experiments for PCMI effects during RIA experiments

In-Memory, Fully-Parallel Coupling of GeN-Foam and OFFBEAT: Towards a New Milestone in High-Fidelity, Finite-Volume Nuclear Reactor Simulation

Analysing hydrogen behaviour in liner claddings using OFFBEAT fuel performance code

The OFFBEAT multi-dimensional fuel behavior solver

Modeling of Sodium Fast Reactors Thermal Expansion Reactivity Feedback using GeN-Foam and Serpent

A reduced order accelerator for time-dependent segregated neutronic solvers

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

Fuel performance code to code comparative analysis for the OECD/NEA MPCMIV benchmark

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

Preliminary Sensitivity Analysis of Time-Dependent Code Outputs in Fuel Performance Models Using OFFBEAT for Future Calibration

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

Two-phase modelling for fission gas sweeping in restructuring nuclear oxide fuel

Investigating the Accuracy of Porous-Medium Treatments in the Analysis of Nuclear Thermal Propulsion Systems

Investigation of the PCMI failure of pre-hydrided Zy-4 cladding during Reactivity Initiated Accidents with ALCYONE and OFFBEAT fuel performance codes

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

Cell-Wise Temperature and Deformation Reactivity Feedback Modeling in Heat Pipe-Cooled Microreactors

OFFBEAT V&V studies for REBEKA tests on cladding ballooning and burst during LOCA conditions

Development of a semi-implicit contact methodology for finite volume stress solvers

Generative AI tools in the nuclear engineering community: A survey-based evaluation of the current adoption and impacts