Luca Cretara

Pubblicazioni

Titolo Pubblicato in Anno
Measurement of fast neutron background in the Gran Sasso underground laboratory using a geyser-concept bubble-chamber EUROPEAN PHYSICAL JOURNAL. C, PARTICLES AND FIELDS 2023
Dimensionless Correlations for Natural Convection Heat Transfer from an Enclosed Horizontal Heated Plate HEAT TRANSFER ENGINEERING 2021
Buoyancy-Induced Convection in Water From a Pair of Horizontal Heated Cylinders Enclosed in a Square Cooled Cavity HEAT TRANSFER ENGINEERING 2021
Effective exploitation of a geyser bubble-chamber equipment as a background-free fast neutron detector EPJ WEB OF CONFERENCES 2021
New dimensionless correlations for the evaluation of the thermal resistances of a district heating twin pipe system APPLIED SCIENCES 2021
Preliminary neutron kinetic. Thermal hydraulic coupled analysis of the ALFRED reactor using PHISICS/RELAP5-3D JOURNAL OF PHYSICS. CONFERENCE SERIES 2020
On the critical energy required for homogeneous nucleation in bubble chambers employed in dark matter searches THE EUROPEAN PHYSICAL JOURNAL. C, PARTICLES AND FIELDS 2019
Effects of the thermodynamic conditions on the acoustic signature of bubble nucleation in superheated liquids used in dark matter search experiments THE EUROPEAN PHYSICAL JOURNAL. C, PARTICLES AND FIELDS 2019
Buoyancy-induced convection in water from a pair of horizontal heated cylinders enclosed in a square cooled cavity HEAT TRANSFER ENGINEERING 2019
The Monte Carlo GPT methodology for the analysis of ratios of functionals bilinear with the real and adjoint neutron fluxes ANNALS OF NUCLEAR ENERGY 2017
MOSCAB: a geyser-concept bubble chamber to be used in a dark matter search THE EUROPEAN PHYSICAL JOURNAL. C, PARTICLES AND FIELDS 2017

ERC

  • PE8_6

KET

  • Sustainable technologies & development

Interessi di ricerca

- Nuclear reactor physics modeling and neutronics design analysis

- Neutronic/thermal hydraulic coupling transient simulation in nuclear safety analysis 

- Generalized perturbation methods (GPT) for sensitivity and uncertainty analysis used for design, operational and nuclear reactor burn-up studies

- Deterministic and Monte Carlo codes for nuclear reactor analysis

- Ionizing particle transport phenomena

- Neutron detector design and simulation (bubble chamber detector) 

- Industrial plants Reliability Analysis 

- Probabilistic Safety Analysis (PSA), Human Reliability Analysis (HRA)

- Safety Analysis applied to Nuclear Decommissioning plant.

 

  

 

Keywords

Monte Carlo methods
Monte Carlo simulations
neutronics
nuclear accidents
human reliability analysis
reliability analysis
Decommissioning

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