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Development of a multiphysics model for the study of fuel compressibility effects in the Molten Salt Fast Reactor

Chemical engineering science, 2019-01, Vol.193, p.379-393

2019

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Role of micrometric roughness on anti-ice properties and durability of hierarchical super-hydrophobic aluminum surfaces

Surface & coatings technology, 2019-09, Vol.374, p.549-556

2019

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Development of an SP3 neutron transport solver for the analysis of the Molten Salt Fast Reactor

Nuclear engineering and design, 2019-05, Vol.346, p.209-219

2019

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Analytical and numerical investigation of the heat exchange effect on the dynamic behaviour of natural circulation with internally heated fluids

Chemical engineering science, 2016-05, Vol.145, p.108-125

2016

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Stability analysis of the Supercritical Water Reactor by means of the root locus criterion

Nuclear engineering and design, 2018-11, Vol.338, p.137-157

2018

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Dynamic stability of natural circulation loops for single phase fluids with internal heat generation

Chemical engineering science, 2015-04, Vol.126, p.573-583

2015

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The influence of the wall thermal inertia over a single-phase natural convection loop with internally heated fluids

Chemical engineering science, 2016-10, Vol.153, p.411-433

2016

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Assessment of analytical and numerical models on experimental data for the study of single-phase natural circulation dynamics in a vertical loop

Chemical engineering science, 2017-04, Vol.162, p.262-283

2017

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Stability analysis by means of information entropy: Assessment of a novel method against natural circulation experimental data

Chemical engineering science, 2017-07, Vol.166, p.220-234

2017

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A new approach for nuclear reactor analysis based on complex network theory

Progress in nuclear energy (New series), 2019-04, Vol.112, p.96-106

2019

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A reduced order model for fission gas diffusion in columnar grains

Nuclear Engineering and Technology, 2023, 55(11), , pp.3983-3995

2023

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Stability analysis of the Generation-IV nuclear reactors by means of the root locus criterion

Progress in nuclear energy (New series), 2018-07, Vol.106, p.316-334

2018

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An extended version of the SERPENT-2 code to investigate fuel burn-up and core material evolution of the Molten Salt Fast Reactor

Journal of nuclear materials, 2013-10, Vol.441 (1-3), p.473-486

2013

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The longevity of light water-cooled large-scale nuclear reactors: A holistic perspective

Nuclear engineering and design, 2024-02, Vol.417, p.112830, Article 112830

2024

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Continuum solvation models in chemical physics: from theory to applications.

1, 2008

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A CFD-based simulation tool for the stability analysis of natural circulation systems

Progress in nuclear energy (New series), 2019-11, Vol.117, p.103093, Article 103093

2019

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Adult Onset Vitiligo: Multivariate Analysis Suggests the Need for a Thyroid Screening

BioMed research international, 2016-01, Vol.2016 (2016), p.1-5

2016

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VOID COEFFICIENT SENSITIVITY ANALYSIS FOR THE TRIGA MARK II REACTOR AT L.E.N.A. (UNIPV)

EPJ Web of conferences, 2021, Vol.247, p.15005

2021

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A multi-physics time-dependent model for the Lead Fast Reactor single-channel analysis

Nuclear engineering and design, 2013-03, Vol.256, p.14-27

2013

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TRIGA reactor absolute neutron flux measurement using activated isotopes

Progress in nuclear energy (New series), 2014-01, Vol.70, p.249-255

2014

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Monte Carlo integrated approach to radiological characterization for nuclear facilities decommissioning

Radiation effects and defects in solids, 2018-10, Vol.173 (9-10), p.772-783

2018

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Development of a control-oriented simulator for a LFR demonstrator

Nuclear engineering and design, 2013-09, Vol.262, p.319-339

2013

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Setting-up a control-oriented model for simulation of TRIGA Mark II dynamic response

Nuclear engineering and design, 2018-05, Vol.331, p.103-115

2018

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An Arbitrary Lagrangian-Eulerian, coupled neutronics-shock physics model for the analysis of shockwave implosion of solid fissile materials

Annals of nuclear energy, 2020-06, Vol.141, p.107322, Article 107322

2020

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Pressure drops prediction in gas–liquid mixtures flowing upflow in vertical ducts

Progress in nuclear energy (New series), 2014-03, Vol.71, p.142-151

2014

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Development of a multiphysics model for the study of fuel compressibility effects in the Molten Salt Fast Reactor

Role of micrometric roughness on anti-ice properties and durability of hierarchical super-hydrophobic aluminum surfaces

Development of an SP3 neutron transport solver for the analysis of the Molten Salt Fast Reactor

Analytical and numerical investigation of the heat exchange effect on the dynamic behaviour of natural circulation with internally heated fluids

Stability analysis of the Supercritical Water Reactor by means of the root locus criterion

Dynamic stability of natural circulation loops for single phase fluids with internal heat generation

The influence of the wall thermal inertia over a single-phase natural convection loop with internally heated fluids

Assessment of analytical and numerical models on experimental data for the study of single-phase natural circulation dynamics in a vertical loop

Stability analysis by means of information entropy: Assessment of a novel method against natural circulation experimental data

A new approach for nuclear reactor analysis based on complex network theory

A reduced order model for fission gas diffusion in columnar grains

Stability analysis of the Generation-IV nuclear reactors by means of the root locus criterion

An extended version of the SERPENT-2 code to investigate fuel burn-up and core material evolution of the Molten Salt Fast Reactor

The longevity of light water-cooled large-scale nuclear reactors: A holistic perspective

Continuum solvation models in chemical physics: from theory to applications.

A CFD-based simulation tool for the stability analysis of natural circulation systems

Adult Onset Vitiligo: Multivariate Analysis Suggests the Need for a Thyroid Screening

VOID COEFFICIENT SENSITIVITY ANALYSIS FOR THE TRIGA MARK II REACTOR AT L.E.N.A. (UNIPV)

A multi-physics time-dependent model for the Lead Fast Reactor single-channel analysis

TRIGA reactor absolute neutron flux measurement using activated isotopes

Monte Carlo integrated approach to radiological characterization for nuclear facilities decommissioning

Development of a control-oriented simulator for a LFR demonstrator

Setting-up a control-oriented model for simulation of TRIGA Mark II dynamic response

An Arbitrary Lagrangian-Eulerian, coupled neutronics-shock physics model for the analysis of shockwave implosion of solid fissile materials

Pressure drops prediction in gas–liquid mixtures flowing upflow in vertical ducts

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