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Study of the energy calibration of the DEAP-3600 detector using Na-22 source data and simulations

Journal of instrumentation, 2024-05, Vol.19 (5), p.C05030

Luzzi, L.

2024

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SCIANTIX: A new open source multi-scale code for fission gas behaviour modelling designed for nuclear fuel performance codes

Journal of nuclear materials, 2020-04, Vol.532, p.152042, Article 152042

2020

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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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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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Modeling high burnup structure in oxide fuels for application to fuel performance codes. part I: High burnup structure formation

Journal of nuclear materials, 2020-10, Vol.539, p.152296, Article 152296

2020

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Modeling intra-granular fission gas bubble evolution and coarsening in uranium dioxide during in-pile transients

Journal of nuclear materials, 2020-09, Vol.538 (C), p.152195, Article 152195

2020

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Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS

Journal of nuclear materials, 2017-04, Vol.486 (C), p.96-110

2017

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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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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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Modelling of thermal conductivity and melting behaviour of minor actinide-MOX fuels and assessment against experimental and molecular dynamics data

Journal of nuclear materials, 2021-12, Vol.557, p.153312, Article 153312

2021

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An effective numerical algorithm for intra-granular fission gas release during non-equilibrium trapping and resolution

Journal of nuclear materials, 2018-10, Vol.509 (C), p.687-699

2018

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A surrogate model for the helium production rate in fast reactor MOX fuels

Nuclear Engineering and Technology, 2023, 55(8), , pp.3071-3079

2023

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On the use of spectral algorithms for the prediction of short-lived volatile fission product release: Methodology for bounding numerical error

Nuclear engineering and technology, 2022-04, Vol.54 (4), p.1195-1205

2022

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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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Uncertainty and sensitivity analysis of fission gas behavior in engineering-scale fuel modeling

Journal of nuclear materials, 2015-01, Vol.456, p.398-408

2015

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Application of the SCIANTIX fission gas behaviour module to the integral pin performance in sodium fast reactor irradiation conditions

Nuclear Engineering and Technology, 2022, 54(7), , pp.2395-2407

2022

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Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications

Journal of nuclear materials, 2020-12, Vol.541, p.152410, Article 152410

2020

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Multiscale modeling of fission gas behavior in U3Si2 under LWR conditions

Journal of nuclear materials, 2019-08, Vol.522, p.97-110

2019

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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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Physics-based modelling and validation of inter-granular helium behaviour in SCIANTIX

Nuclear Engineering and Technology, 2022, 54(7), , pp.2367-2375

2022

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Incidence and risk factors for respiratory tract bacterial colonization and infection in lung transplant recipients

European journal of clinical microbiology & infectious diseases, 2021-06, Vol.40 (6), p.1271-1282

2021

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On the intra-granular behaviour of a cocktail of inert gases in oxide nuclear fuel: Methodological recommendation for accelerated experimental investigation

Nuclear Engineering and Technology, 2022, 54(5), , pp.1929-1934

2022

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Extension and application of the TRANSURANUS code to the normal operating conditions of the MYRRHA reactor

Nuclear engineering and design, 2022-01, Vol.386, p.111581, Article 111581

2022

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Isotropic softening model for fuel cracking in BISON

Nuclear engineering and design, 2019-02, Vol.342, p.257-263

2019

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Study of the energy calibration of the DEAP-3600 detector using Na-22 source data and simulations

SCIANTIX: A new open source multi-scale code for fission gas behaviour modelling designed for nuclear fuel performance codes

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

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

Modeling high burnup structure in oxide fuels for application to fuel performance codes. part I: High burnup structure formation

Modeling intra-granular fission gas bubble evolution and coarsening in uranium dioxide during in-pile transients

Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS

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

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

Modelling of thermal conductivity and melting behaviour of minor actinide-MOX fuels and assessment against experimental and molecular dynamics data

An effective numerical algorithm for intra-granular fission gas release during non-equilibrium trapping and resolution

A surrogate model for the helium production rate in fast reactor MOX fuels

On the use of spectral algorithms for the prediction of short-lived volatile fission product release: Methodology for bounding numerical error

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

Uncertainty and sensitivity analysis of fission gas behavior in engineering-scale fuel modeling

Application of the SCIANTIX fission gas behaviour module to the integral pin performance in sodium fast reactor irradiation conditions

Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications

Multiscale modeling of fission gas behavior in U3Si2 under LWR conditions

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

Physics-based modelling and validation of inter-granular helium behaviour in SCIANTIX

Incidence and risk factors for respiratory tract bacterial colonization and infection in lung transplant recipients

On the intra-granular behaviour of a cocktail of inert gases in oxide nuclear fuel: Methodological recommendation for accelerated experimental investigation

Extension and application of the TRANSURANUS code to the normal operating conditions of the MYRRHA reactor

Isotropic softening model for fuel cracking in BISON

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