| 2024 |
Hypothetical porous medium concept as a virtual swirl tape: A novel modelling technique towards efficient CFD simulation of swirl tape cooling pipe |
Articolo in rivista |
Vai |
| 2023 |
Thermomechanical and Thermofluid-Dynamic Coupled Analysis of the Top Cap Region of the Water-Cooled Lithium Lead Breeding Blanket for the EU DEMO Fusion Reactor |
Articolo in rivista |
Vai |
| 2023 |
Thermal-hydraulic study of the Primary Heat Transport System of the DEMO Divertor Cassette Body |
Articolo in rivista |
Vai |
| 2022 |
Production and transport modelling of Po-210 in DEMO reactor |
Articolo in rivista |
Vai |
| 2022 |
Development and application of an alternative modelling approach for the thermo-mechanical analysis of a DEMO water-cooled lithium lead breeding blanket segment |
Articolo in rivista |
Vai |
| 2022 |
On the modelling of tritium transport phenomena at fluid-structure interfaces |
Articolo in rivista |
Vai |
| 2021 |
Multiphysics Optimization for First Wall Design Enhancement in Water-Cooled Breeding Blankets |
Articolo in rivista |
Vai |
| 2021 |
Integrated design of breeding blanket and ancillary systems related to the use of helium or water as a coolant and impact on the overall plant design |
Articolo in rivista |
Vai |
| 2021 |
Structural assessment of the EU-DEMO WCLL Central Outboard Blanket segment under normal and off-normal operating conditions |
Articolo in rivista |
Vai |
| 2021 |
Conceptual design of the main Ancillary Systems of the ITER Water Cooled Lithium Lead Test Blanket System |
Articolo in rivista |
Vai |
| 2020 |
Investigation of the DEMO WCLL Breeding Blanket Cooling Water Activation |
Articolo in rivista |
Vai |
| 2020 |
Progress of the conceptual design of the European DEMO breeding blanket, tritium extraction and coolant purification systems |
Articolo in rivista |
Vai |
| 2020 |
Assessment of DEMO WCLL breeding blanket primary heat transfer system isolation valve absorbed doses due to activated water |
Articolo in rivista |
Vai |
| 2019 |
A multi-physics integrated approach to breeding blanket modelling and design |
Articolo in rivista |
Vai |
| 2019 |
Parametric study of the influence of First Wall cooling water on the Water Cooled Lithium Lead Breeding Blanket nuclear response |
Articolo in rivista |
Vai |
| 2019 |
Validation of Multi-Physics Integrated Procedure for the HCPB Breeding Blanket |
Articolo in rivista |
Vai |
| 2019 |
Recent progress in developing a feasible and integrated conceptual design of the WCLL BB in EUROfusion project |
Articolo in rivista |
Vai |
| 2018 |
Numerical assessment of the thermomechanical behaviour of the DEMO Water-Cooled Lithium Lead inboard blanket equatorial module |
Articolo in rivista |
Vai |
| 2018 |
Multi-Module vs. Single-Module concept: Comparison of thermomechanical performances for the DEMO Water-Cooled Lithium Lead breeding blanket |
Articolo in rivista |
Vai |
| 2017 |
Structural analysis of the back supporting structure of the DEMO WCLL outboard blanket |
Articolo in rivista |
Vai |
| 2017 |
Assessment of the importance of neutron multiplication for tritium production |
Articolo in rivista |
Vai |
| 2017 |
On the thermo-mechanical behaviour of DEMO water-cooled lithium lead equatorial outboard blanket module |
Articolo in rivista |
Vai |
| 2016 |
Optimization of the breeder zone cooling tubes of the DEMO Water-Cooled Lithium Lead breeding blanket |
Articolo in rivista |
Vai |
| 2016 |
On the optimization of the first wall of the DEMO water-cooled lithium lead outboard breeding blanket equatorial module |
Articolo in rivista |
Vai |
| 2016 |
First Flight Escape Probability and Uncollided Flux of Nuclear Particles in Convex Bodies with Spherical Symmetry |
Articolo in rivista |
Vai |
| 2015 |
Analysis of the thermo-mechanical behaviour of the DEMO Water-Cooled Lithium Lead breeding blanket module under normal operation steady state conditions |
Articolo in rivista |
Vai |
| 2014 |
Analysis of the thermo-mechanical behaviour of the DEMO Water-Cooled Lithium Lead breeding blanket module under normal operation steady state conditions |
Proceedings |
Vai |
| 2014 |
Validazione e Verifica (V&V) di CATHARE2 e TRACE sul Programma Sperimentale SPES-2 |
Monografia |
Vai |
| 2014 |
Analysis of a Station Black-Out transient in SMR by using the TRACE and RELAP5 code |
Proceedings |
Vai |
| 2014 |
On the numerical assessment of the thermo-mechanical performances of the DEMO Helium-Cooled Pebble Bed breeding blanket module |
Articolo in rivista |
Vai |
| 2013 |
Fattibilità di una diversa configurazione della facility SPES-3 |
Monografia |
Vai |
| 2013 |
Analysis of a Generation 3+ Pressurised Water Reactor plant response to a postulated Station Black Out |
Proceedings |
Vai |
| 2013 |
Nuclear Analysis of an ITER Blanket Module |
Articolo in rivista |
Vai |
| 2013 |
On the adoption of the Monte Carlo method to solve one-dimensional steady state thermal diffusion problems for non-uniform solids |
Articolo in rivista |
Vai |
| 2012 |
Adeguamento dello SPES2 per Prove di Sicurezza. Analisi Preliminari per La Simulazione di un Incidente Tipo Fukushima su SPES-2 |
Monografia |
Vai |
| 2012 |
Analisi Incidentali Deterministiche e Utilizzo di Simulatori di Impianto a Supporto delle Verifiche di Sicurezza. Sviluppo e Messa a Punto di un Modello di un Impianto PWR (EPR like) per Preliminari Analisi con il Codice TRACE di Eventi di Station Blackout |
Monografia |
Vai |
| 2012 |
ANALYSES OF THE SPES-3 DESIGN AND BEYOND DESIGN ACCIDENT
CONDITION BY USING TRACE CODE |
Proceedings |
Vai |
| 2012 |
A neutron point kinetic model for fusion relevant calculations |
Articolo in rivista |
Vai |
| 2011 |
A Training Experience of Operators with the AGN-201 “Costanza” Research Reactor of Palermo University |
Proceedings |
Vai |
| 2011 |
Analysis of the SPES-3 direct vessel injection line break by using TRACE code |
Proceedings |
Vai |
| 2011 |
Modifiche del codice RELAP5/MOD3.2.b per lo studio delle perdite di carico e dello scambio termico in condotti elicoidali interessati da deflussi bifase: validazione attraverso gli esperimenti effettuati dal Politecnico di Milano presso l’impianto SIET di Piacenza |
Monografia |
Vai |
| 2011 |
Implementazione ed utilizzo di simulatori semplificati “Desktop” |
Monografia |
Vai |
| 2011 |
Analisi Mediante Il Codice TRACE Delle Principali Fenomenologie Caratterizzanti Il Transitorio Conseguente Ad Una Rottura A Ghigliottina Nella Linea DVI dell’Impianto Sperimentale SPES-3 |
Monografia |
Vai |
| 2010 |
Sul numero delle disposizioni delle N parti dell'intero M nel caso in cui nessuna delle parti possa essere superiore a Q |
Articolo in rivista |
Vai |
| 2010 |
TRACE input model for SPES3 facility |
Monografia |
Vai |
| 2010 |
Education and Research in Nuclear Engineering and Radiological Protection at Nuclear Engineering Department of Palermo University |
Proceedings |
Vai |
| 2010 |
Applicazione del metodo Monte Carlo a problemi monodimensionali di conduzione termica stazionaria in sistemi con conducibilità dipendente dalla posizione |
Articolo in rivista |
Vai |
| 2010 |
Thermal-mechanical and thermal-hydraulic integrated study of the Helium-Cooled Lithium Lead Test Blanket Module |
Articolo in rivista |
Vai |
| 2010 |
Modifiche del Codice RELAP5 per lo Studio delle Perdite di Carico in Generatori di Vapore a Tubi Elicoidali Interessati da Flussi Bifase |
Monografia |
Vai |
| 2009 |
Assessment of the Possible Lay-Out Influence on the HCLL-TBM Nuclear Response |
Articolo in rivista |
Vai |
| 2009 |
Una variante del problema dell'ago di Buffon e verifica con il metodo Monte Carlo |
Abstract in rivista |
Vai |
| 2009 |
On the improved current pulse method for the dynamic assessment of thermal diffusive properties |
Articolo in rivista |
Vai |
| 2009 |
Study of the helium-cooled lithium lead test blanket module nuclear behaviour under irradiation in ITER |
Articolo in rivista |
Vai |
| 2008 |
A study of the potential influence of frame coolant distribution on the radiation-induced damage of HCLL-TBM structural material |
Articolo in rivista |
Vai |
| 2008 |
Probabilità di fuga di "particelle" nucleari da corpi a simmetria sferica |
Articolo in rivista |
Vai |
| 2008 |
A Monte Carlo study on the possible lay-out influence in the HCLL-TBM nuclear response |
Proceedings |
Vai |
| 2007 |
On the effects of the supporting frame on the radiation-induced damage of HCLL-TBM structural material |
Articolo in rivista |
Vai |
| 2007 |
A study of the potential influence of frame coolant on HCLL-TBM nuclear response |
Articolo in rivista |
Vai |
| 2007 |
Studies on the AGN - 201 "COSTANZA" Research Reactor |
Proceedings |
Vai |
| 2006 |
On the influence of the supporting frame on the nuclear response of the Helium-Cooled Lithium Lead Test Blanket Module for ITER |
Articolo in rivista |
Vai |
| 2005 |
On the nuclear response of the helium-cooled lithium lead test blanket module in ITER |
Articolo in rivista |
Vai |
| 2005 |
On the AGN - 201 "COSTANZA" Research Reactor at the Department of Nuclear Engineering of the University of Palermo |
Proceedings |
Vai |
| 2005 |
On the effects of the supporting frame on the radiation-induced damage of HCLL-TBM structural material |
Proceedings |
Vai |
| 2003 |
On the nuclear response of the water-cooled Pb-17Li test blanket module for ITER-FEAT |
Articolo in rivista |
Vai |
| 2002 |
Neutronic and photonic analysis of the water-cooled Pb-17Li test blanket module for ITER-FEAT |
Articolo in rivista |
Vai |
