| 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 |
ADRANOS: A numerical tool developed to analyse coolant operating conditions of the EU-DEMO divertor |
Articolo in rivista |
Vai |
| 2023 |
Exploratory Thermo-Mechanical Assessment of the Bottom Cap Region of the EU DEMO Water-Cooled Lead Lithium Central Outboard Blanket Segment |
Articolo in rivista |
Vai |
| 2023 |
Exploratory study of the EU-DEMO Water-Cooled Lithium Lead breeding blanket behaviour in case of loss of cooling capability |
Articolo in rivista |
Vai |
| 2023 |
Design and Integration of the EU-DEMO Water-Cooled Lead Lithium Breeding Blanket |
Articolo in rivista |
Vai |
| 2023 |
Study of the thermo-mechanical performances of the EU-DEMO Water-Cooled Lead Lithium Left Outboard Blanket segment |
Articolo in rivista |
Vai |
| 2023 |
Thermofluid-dynamic assessment of the EU-DEMO divertor single-circuit cooling option |
Articolo in rivista |
Vai |
| 2023 |
Thermal-hydraulic study of the Primary Heat Transport System of the DEMO Divertor Cassette Body |
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 |
Current status of MELCOR 2.2 for fusion safety analyses |
Articolo in rivista |
Vai |
| 2023 |
Structural assessment of the EU-DEMO water-cooled lead lithium central outboard blanket segment adopting the sub-modelling technique |
Articolo in rivista |
Vai |
| 2023 |
Development of a thermal-hydraulic model of the EU-DEMO Water Cooled Lithium Lead Breeding Blanket Primary Heat Transport System |
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 |
Preliminary thermal optimization and investigation of the overall structural behaviour of the EU-DEMO water-cooled lead lithium left outboard blanket segment |
Articolo in rivista |
Vai |
| 2022 |
Cold Leg LBLOCA uncertainty analysis using TRACE/DAKOTA coupling |
Articolo in rivista |
Vai |
| 2022 |
On the modelling of tritium transport phenomena at fluid-structure interfaces |
Articolo in rivista |
Vai |
| 2022 |
A Numerical Approach to Study Shell-Side Fluid Flow in Shell-and-Tube Heat Exchangers |
Articolo in rivista |
Vai |
| 2022 |
Analysis of the Thermo-Mechanical Behaviour of the EU DEMO Water-Cooled Lithium Lead Central Outboard Blanket Segment under an Optimized Thermal Field |
Articolo in rivista |
Vai |
| 2022 |
Production and transport modelling of Po-210 in DEMO reactor |
Articolo in rivista |
Vai |
| 2022 |
Tokamak cooling systems and power conversion system options |
Articolo in rivista |
Vai |
| 2022 |
Divertor of the European DEMO: Engineering and technologies for power exhaust |
Articolo in rivista |
Vai |
| 2022 |
Thermo-Mechanical Analysis and Design Update of the Top Cap Region of the DEMO Water-Cooled Lithium Lead Central Outboard Blanket Segment |
Articolo in rivista |
Vai |
| 2022 |
Special Issue on Structural and Thermo-Mechanical Analyses in Nuclear Fusion Reactors |
Nota o commento |
Vai |
| 2021 |
Determination of a pre-heating sequence for the DONES Target Assembly |
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 |
| 2021 |
Preliminary thermal-hydraulic analysis of the EU-DEMO Helium-Cooled Pebble Bed fusion reactor by using the RELAP5-3D system code |
Articolo in rivista |
Vai |
| 2021 |
Hydraulic characterization of the full scale mock-up of the demo divertor outer vertical target |
Articolo in rivista |
Vai |
| 2021 |
Multiphysics Optimization for First Wall Design Enhancement in Water-Cooled Breeding Blankets |
Articolo in rivista |
Vai |
| 2021 |
Hydraulic assessment of an upgraded pipework arrangement for the DEMO divertor plasma facing components cooling circuit |
Articolo in rivista |
Vai |
| 2021 |
Thermal-hydraulic study of the DEMO divertor cassette body cooling circuit equipped with a liner and two reflector plates |
Articolo in rivista |
Vai |
| 2021 |
Pre-conceptual design of EU-DEMO divertor primary heat transfer systems |
Articolo in rivista |
Vai |
| 2021 |
Structural assessment of a whole toroidal sector of the HELIAS 5-B breeding blanket |
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 |
The demo water-cooled lead–lithium breeding blanket: Design status at the end of the pre-conceptual design phase |
Articolo in rivista |
Vai |
| 2020 |
On the thermal-hydraulic performances of the DEMO divertor cassette body cooling circuit equipped with a liner |
Articolo in rivista |
Vai |
| 2020 |
On the numerical assessment of the thermal-hydraulic operating map of the DEMO Divertor Plasma Facing Components cooling circuit |
Articolo in rivista |
Vai |
| 2020 |
Preliminary design of the top cap of DEMO Water-Cooled Lithium Lead breeding blanket segments |
Articolo in rivista |
Vai |
| 2020 |
Eurofusion-DEMO Divertor - Cassette Design and Integration |
Articolo in rivista |
Vai |
| 2020 |
Investigation of the DEMO WCLL Breeding Blanket Cooling Water Activation |
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 |
| 2020 |
Assessment of Fatigue Effects Induced by Fast Beam Transients in the IFMIF-DONES Li Target |
Articolo in rivista |
Vai |
| 2020 |
Analytical and Numerical Assessment of Thermally Induced Pressure Waves in the IFMIF-DONES Liquid-Lithium Target |
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 |
On the impact of the heat transfer modelling approach on the prediction of EU-DEMO WCLL breeding blanket thermal performances |
Articolo in rivista |
Vai |
| 2020 |
Parametric study of the influence of double-walled tubes layout on the DEMO WCLL breeding blanket thermal performances |
Articolo in rivista |
Vai |
| 2020 |
Safety analysis of the DONES primary heat removal system |
Articolo in rivista |
Vai |
| 2019 |
Further improvements in the structural analysis of DEMO Divertor Cassette body and design assessment according to RCC-MRx |
Articolo in rivista |
Vai |
| 2019 |
Thermal-hydraulic optimisation of the DEMO divertor cassette body cooling circuit equipped with a liner |
Articolo in rivista |
Vai |
| 2019 |
Hydraulic analysis of EU-DEMO divertor plasma facing components cooling circuit under nominal operating scenarios |
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 |
On the thermal dynamic behaviour of the helium-cooled DEMO fusion reactor |
Articolo in rivista |
Vai |
| 2019 |
The design of the DONES lithium target system |
Articolo in rivista |
Vai |
| 2019 |
On the effects of the Double-Walled Tubes lay-out on the DEMO WCLL breeding blanket module thermal behavior |
Articolo in rivista |
Vai |
| 2019 |
A multi-physics integrated approach to breeding blanket modelling and design |
Articolo in rivista |
Vai |
| 2019 |
Progress in the design development of EU DEMO helium-cooled pebble bed primary heat transfer system |
Articolo in rivista |
Vai |
| 2019 |
Parametric thermal analysis for the optimization of Double Walled Tubes layout in the Water Cooled Lithium Lead inboard blanket of DEMO fusion reactor |
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 |
| 2019 |
Structural verification and manufacturing procedures of the cooling system, for DEMO divertor target (OVT) |
Articolo in rivista |
Vai |
| 2019 |
Thermal-hydraulic and thermo-mechanical simulations of Water-Heavy Liquid Metal interactions towards the DEMO WCLL breeding blanket design |
Articolo in rivista |
Vai |
| 2019 |
Conceptual design of the enhanced coolant purification systems for the European HCLL and HCPB test blanket modules |
Articolo in rivista |
Vai |
| 2019 |
Updated design and integration of the ancillary circuits for the European Test Blanket Systems |
Articolo in rivista |
Vai |
| 2019 |
Validation of Multi-Physics Integrated Procedure for the HCPB Breeding Blanket |
Articolo in rivista |
Vai |
| 2019 |
On the effect of stiffening plates configuration on the DEMO Water Cooled Lithium Lead Breeding Blanket module thermo-mechanical behaviour |
Articolo in rivista |
Vai |
| 2018 |
Development of a Two-Dimensional Simplified Tool for the Analysis of the Cooling of the ITER TF Winding Pack |
Articolo in rivista |
Vai |
| 2018 |
Advancements in DEMO WCLL breeding blanket design and integration |
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 |
| 2018 |
On the thermal-hydraulic optimization of DEMO divertor plasma facing components cooling circuit |
Articolo in rivista |
Vai |
| 2018 |
On the thermal and thermomechanical assessment of the “Optimized Conservative” helium-cooled lithium lead breeding blanket concept for DEMO |
Articolo in rivista |
Vai |
| 2018 |
Preliminary design of EU DEMO helium-cooled breeding blanket primary heat transfer system |
Articolo in rivista |
Vai |
| 2018 |
Recent Progress in the WCLL Breeding Blanket Design for the DEMO Fusion Reactor |
Articolo in rivista |
Vai |
| 2018 |
Thermomechanical analysis supporting the preliminary engineering design of DONES target assembly |
Articolo in rivista |
Vai |
| 2018 |
Progress in EU Breeding Blanket design and integration |
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 |
Computational thermofluid-dynamic analysis of DEMO divertor cassette body cooling circuit |
Articolo in rivista |
Vai |
| 2017 |
Assessment of the importance of neutron multiplication for tritium production |
Articolo in rivista |
Vai |
| 2017 |
Analysis of steady state thermal-hydraulic behaviour of the DEMO divertor cassette body cooling circuit |
Articolo in rivista |
Vai |
| 2017 |
Progress in the initial design activities for the European DEMO divertor: Subproject "Cassette" |
Articolo in rivista |
Vai |
| 2017 |
Thermo-mechanical analysis of irradiation swelling and design optimization of the IFMIF target assembly with bayonet backplate |
Articolo in rivista |
Vai |
| 2017 |
Structural analysis of the back supporting structure of the DEMO WCLL outboard blanket |
Articolo in rivista |
Vai |
| 2017 |
Thermal-hydraulic behaviour of the DEMO divertor plasma facing components cooling circuit |
Articolo in rivista |
Vai |
| 2017 |
On the thermo-mechanical behaviour of DEMO water-cooled lithium lead equatorial outboard blanket module |
Articolo in rivista |
Vai |
| 2017 |
WCLL breeding blanket design and integration for DEMO 2015: status and perspectives |
Articolo in rivista |
Vai |
| 2017 |
Thermal optimization of the Helium-Cooled Lithium Lead breeding zone layout design regarding TBR enhancement |
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 |
Draining and drying process development of the Tokamak Cooling Water System of ITER |
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 |
Design and manufacturing feasibility of ITER TBM Frame and Dummy TBMs |
Articolo in rivista |
Vai |
| 2016 |
On the hydraulic behaviour of ITER Shield Blocks #14 and #08. Computational analysis and comparison with experimental tests |
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 |
| 2015 |
A computational procedure for the investigation of whipping effect on ITER High Energy Piping and its application to the ITER divertor primary heat transfer system |
Articolo in rivista |
Vai |
| 2015 |
Analysis of the steady state hydraulic behaviour of the ITER blanket cooling system |
Articolo in rivista |
Vai |
| 2015 |
Analysis of the thermomechanical behavior of the IFMIF bayonet target assembly under design loading scenarios |
Articolo in rivista |
Vai |
| 2015 |
Optimization of the first wall for the DEMO water cooled lithium lead blanket |
Articolo in rivista |
Vai |
| 2015 |
Numerical simulation of the transient thermal-hydraulic behaviour of the ITER blanket cooling system under the draining operational procedure |
Articolo in rivista |
Vai |
| 2014 |
Hydraulic Analysis of Blanket Cooling System |
Monografia |
Vai |
| 2014 |
Status of ITER TBM port plug conceptual design and analyses |
Articolo in rivista |
Vai |
| 2014 |
A computational procedure for the investigation of whipping effect on ITER High Energy Piping and its application to the ITER divertor primary heat transfer system |
eedings |
Vai |
| 2014 |
Analysis of the steady state thermal-hydraulic behaviour of the ITER blanket cooling system |
eedings |
Vai |
| 2014 |
Optimization of the First Wall for the DEMO Water Cooled Lithium Lead Blanket |
eedings |
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 |
| 2014 |
Start-up and shutdown thermomechanical transient analyses of the IFMIF European lithium target system |
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 |
eedings |
Vai |
| 2014 |
Numerical simulation of the transient thermal-hydraulic behaviour of the ITER blanket cooling system under the draining operational procedure |
eedings |
Vai |
| 2014 |
Hydraulic Analysis of Blanket Cooling System |
Monografia |
Vai |
| 2014 |
Analysis of the thermo-mechanical behaviour of IFMIF target assembly integrated with its support framework |
Monografia |
Vai |
| 2014 |
Steady state thermo-mechanical analysis of the IFMIF Lithium target system with bayonet backplate under design conditions |
eedings |
Vai |
| 2013 |
Analysis of the thermo-mechanical behaviour of IFMIF target assembly |
Monografia |
Vai |
| 2013 |
Analysis of a Generation 3+ Pressurised Water Reactor plant response to a postulated Station Black Out |
eedings |
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 |
| 2013 |
Engineering design and steady state thermomechanical analysis of the IFMIF European lithium target system |
eedings |
Vai |
| 2013 |
Analysis of the thermo-mechanical behaviour of IFMIF fast disconnecting system |
Monografia |
Vai |
| 2013 |
On the thermomechanical behavior of the European target assembly design of IFMIF-EVEDA lithium test loop under start-up transient scenarios |
Articolo in rivista |
Vai |
| 2013 |
Fattibilità di una diversa configurazione della facility SPES-3 |
Monografia |
Vai |
| 2013 |
Design, manufacturing and testing of a fast disconnecting system for the European target assembly concept of IFMIF |
eedings |
Vai |
| 2013 |
Nuclear Analysis of an ITER Blanket Module |
Articolo in rivista |
Vai |
| 2013 |
Preliminary design of a Water Cooled Lithium Lead blanket concept for DEMO reactor |
Monografia |
Vai |
| 2013 |
Hydraulic Analysis of Blanket Cooling System |
Monografia |
Vai |
| 2013 |
Water Cooled First Wall optimization for WCLL DEMO reactor |
Monografia |
Vai |
| 2013 |
Hydraulic Analysis of the CDR Design of the ITER TBM Port Plug |
Monografia |
Vai |
| 2013 |
The European contribution to the development and validation activities for the design of IFMIF lithium facility |
Articolo in rivista |
Vai |
| 2012 |
Status of ceramic breeder pebble bed thermo-mechanics R&D and impact on breeder material mechanical strength |
Articolo in rivista |
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 |
On the Improved Current Pulse method for the thermal diffusive characterization of lithiated ceramic pebble beds |
Articolo in rivista |
Vai |
| 2012 |
A neutron point kinetic model for fusion relevant calculations |
Articolo in rivista |
Vai |
| 2012 |
Thermal-hydraulic and thermal-structural analyses report of DEMO WCLL blanket |
Monografia |
Vai |
| 2012 |
Analysis of the thermo-mechanical behaviour of IFMIF Target Assembly |
Monografia |
Vai |
| 2012 |
On the investigation of Lithium Methatitanate pebble bed thermal diffusive properties by the Improved Current Pulse method |
eedings |
Vai |
| 2012 |
Study of the thermo-mechanical performances of the IFMIF-EVEDA Lithium Test Loop target assembly |
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 |
Thermal-hydraulic and thermal-structural analyses report of DEMO Helium-Cooled Pebble Bed blanket |
Monografia |
Vai |
| 2011 |
A Training Experience of Operators with the AGN-201 “Costanza” Research Reactor of Palermo University |
eedings |
Vai |
| 2011 |
Analysis of the thermo-mechanical behaviour of IFMIF-EVEDA Lithium Test Loop Target Assembly |
Monografia |
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 |
On the computational assessment of the IFMIF-EVEDA Target Assembly thermal behaviour |
eedings |
Vai |
| 2011 |
On thermo-mechanical issues induced by irradiation swelling inside the back-plate of the IFMIF target assembly |
Articolo in rivista |
Vai |
| 2011 |
On the theoretical–numerical study of the ITER Upper Port Plug structure hydraulic behaviour under steady state and draining and drying transient conditions |
Articolo in rivista |
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 |
| 2011 |
Analysis of the SPES-3 direct vessel injection line break by using TRACE code |
eedings |
Vai |
| 2011 |
Hydraulic characterization of the full scale divertor cassette prototype |
Articolo in rivista |
Vai |
| 2011 |
PROVE ED ESPERIMENTI DI VERIFICA DELLA SICUREZZA DEL REATTORE NUCLEARE DI RICERCA AGN-201 “COSTANZA” |
Articolo in rivista |
Vai |
| 2011 |
Electrical Aging Tests on Enameled Wire Exposed to Gamma Irradiation |
eedings |
Vai |
| 2011 |
Thermo-mechanical issues induced by neutron swelling in the IFMIF Target Assembly back-plate |
Monografia |
Vai |
| 2010 |
Thermal-mechanical and thermal-hydraulic integrated study of the Helium-Cooled Lithium Lead Test Blanket Module |
Articolo in rivista |
Vai |
| 2010 |
On the improved current pulse method for the thermal diffusive characterization of lithiated ceramic pebble beds |
eedings |
Vai |
| 2010 |
On the numerical assessment of the thermal-hydraulic behaviour of ITER Upper Port Plug Main Body cooling circuit |
eedings |
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 |
eedings |
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 |
On the theoretical–numerical study of the HEXCALIBER mock-up thermo-mechanical behaviour |
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 |
| 2010 |
On the hyperporous non-linear elasticity model for fusion-relevant pebble beds |
Articolo in rivista |
Vai |
| 2010 |
ITER Upper Port Plug Draining and Drying |
Monografia |
Vai |
| 2009 |
On a computational study of the hydraulic behavior of the ITER divertor cassette full-scale prototype |
eedings |
Vai |
| 2009 |
HEXCALIBER TEST SECTION. Thermo-mechanical analysis |
Monografia |
Vai |
| 2009 |
Assessment of the Possible Lay-Out Influence on the HCLL-TBM Nuclear Response |
Articolo 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 |
| 2009 |
Thermal analysis of the Helium-Cooled Lithium Lead Test Blanket Module to be irradiated in ITER |
eedings |
Vai |
| 2009 |
The hydraulic behaviour of the prototype of on a ITER divertor cassette |
Monografia |
Vai |
| 2008 |
On the numerical and experimental characterisation of the ITER divertor cassette plasma facing component steady state hydraulic behaviour |
eedings |
Vai |
| 2008 |
On the assessment of lithium orthosilicate pebble bed thermal diffusive properties by the improved current pulse method |
eedings |
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 |
A Monte Carlo study on the possible lay-out influence in the HCLL-TBM nuclear response |
eedings |
Vai |
| 2008 |
Experimental tests and thermo-mechanical analyses on the HEXCALIBER mock-up |
Articolo in rivista |
Vai |
| 2008 |
XXVI Congresso Nazionale sulla Trasmissione del Calore |
Curatela |
Vai |
| 2008 |
Thermo-mechanical experiment and analysis on an HCPB-TBM mock-up |
eedings |
Vai |
| 2008 |
Steady state and transient thermal-hydraulic characterization of full-scale ITER divertor plasma facing components |
Articolo in rivista |
Vai |
| 2007 |
Studies on the AGN - 201 "COSTANZA" Research Reactor |
eedings |
Vai |
| 2007 |
The hydraulic behaviour of the simulacrum of the Inner Vertical Target of an ITER divertor cassette |
Monografia |
Vai |
| 2007 |
The hydraulic behaviour of the simulacrum of the Dome Liner of an ITER divertor cassette |
Monografia |
Vai |
| 2007 |
The hydraulic behaviour of the simulacrum of a Plasma Vessel Module of the W 7-X Reactor |
Monografia |
Vai |
| 2007 |
The hydraulic behaviour of the simulacrum of the Outer Vertical Target of an ITER divertor cassette |
Monografia |
Vai |
| 2007 |
A study of the potential influence of frame coolant on HCLL-TBM nuclear response |
Articolo in rivista |
Vai |
| 2007 |
HEXCALIBER TEST SECTION. Preliminary thermo-mechanical analysis |
Monografia |
Vai |
| 2007 |
A constitutive model for the thermo-mechanical behaviour of fusion-relevant pebble beds and its application to the simulation of HELICA mock-up experimental results |
Articolo in rivista |
Vai |
| 2007 |
On the effects of the supporting frame on the radiation-induced damage of HCLL-TBM structural material |
Articolo in rivista |
Vai |
| 2006 |
A constitutive model for the thermo-mechanical behaviour of fusion-relevant pebble beds and its application to the simulation of HELICA mock-up experimental results |
eedings |
Vai |
| 2006 |
Piano di emergenza per il reattore nucleare di ricerca AGN-201 COSTANZA dell’Università di Palermo: presupposti tecnici e valutazioni radiologiche |
eedings |
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 |
| 2006 |
Preparation of HEXCALIBER tests and preliminary thermo-mechanical analyses |
eedings |
Vai |
| 2006 |
Mixed MHD Convection and Tritium Transport in HCLL TBM Breeder Units for the ITER Fusion Reactor |
eedings |
Vai |
| 2006 |
The HELICA mock-up. Experimental results and numerical thermo-mechanical analyses |
eedings |
Vai |
| 2006 |
Progress in the benchmark exercise for analyzing the lithiate breeder pebble bed thermo-mechanical behaviour |
Articolo in rivista |
Vai |
| 2005 |
The ITER divertor cassette. Steady-state characterisation and draining and drying transient hydraulic analyses |
eedings |
Vai |
| 2005 |
On the use of an improved current pulse method for the experimental determination of the thermal diffusive properties of packed pebble beds |
eedings |
Vai |
| 2005 |
On the AGN - 201 "COSTANZA" Research Reactor at the Department of Nuclear Engineering of the University of Palermo |
eedings |
Vai |
| 2005 |
On the nuclear response of the helium-cooled lithium lead test blanket module in ITER |
Articolo in rivista |
Vai |
| 2005 |
Out of Pile Thermo-Mechanical Testing of Breeder Pebble Beds for HCPB TBM for ITER |
eedings |
Vai |
| 2005 |
Steady-state and transient thermal-hydraulic analyses on ITER divertor module |
Articolo in rivista |
Vai |
| 2005 |
On the effects of the supporting frame on the radiation-induced damage of HCLL-TBM structural material |
eedings |
Vai |
| 2005 |
Final report on the test campaigns HELICA I-II performed in HEFUS facility |
Monografia |
Vai |
| 2005 |
Sezione di prova HELICA. Analisi termomeccaniche |
Monografia |
Vai |
| 2005 |
Mixed MHD convection and Tritium transport in fusion-relevant configurations |
Articolo in rivista |
Vai |
| 2004 |
Mixed magnetohydrodynamic convection in poloidal Helium-Cooled Lithium Lead blanket modules of a fusion reactor |
eedings |
Vai |
| 2004 |
Thermo-mechanical testing of Li-ceramic for the helium cooled pebble bed (HCPB) breeding blanket |
Articolo in rivista |
Vai |
| 2004 |
The hydraulic behaviour of the ITER full-scale divertor cassette. The transient analyses |
Monografia |
Vai |
| 2004 |
Final report on the contract EFDA 682 - Preparation of integration and hydraulic tests of full-scale divertor components. |
Monografia |
Vai |
| 2004 |
The hydraulic behaviour of the ITER full-scale divertor cassette. The steady state analyses |
Monografia |
Vai |
| 2004 |
Steady state and transient thermal-hydraulic analyses on ITER divertor cassette |
eedings |
Vai |
| 2003 |
Experimental investigations on the thermal conductivity of packed pebble beds by the current pulse method |
eedings |
Vai |
| 2003 |
On the nuclear response of the water-cooled Pb-17Li test blanket module for ITER-FEAT |
Articolo in rivista |
Vai |
| 2003 |
On the nuclear impact of different coolants in the HCLL-TBM in ITER-FEAT |
Monografia |
Vai |
| 2003 |
MHD Free Convection in Helium-Cooled Lithium-Lead Blanket Modules for the Demonstration Fusion Reactor |
eedings |
Vai |
| 2003 |
Experimental tests on Li-ceramic breeders for the helium cooled pebble bed (HCPB) blanket design |
Articolo in rivista |
Vai |
| 2003 |
On the nuclear response of the HCLL-TBM in ITER-FEAT |
Monografia |
Vai |
| 2003 |
A Semi-Theoretical Approach to a Correlation for the Thermal Conductivity of a Beryllium Pebble Bed |
Articolo in rivista |
Vai |
| 2003 |
La sezione di prova HELICHETTA. Analisi termomeccaniche numeriche e sperimentali |
Monografia |
Vai |
| 2003 |
Studio del comportamento termico di letti di sfere tramite il metodo dell’impulso di corrente |
Monografia |
Vai |
| 2002 |
Neutronic and photonic analysis of the water-cooled Pb-17Li test blanket module for ITER-FEAT |
Articolo in rivista |
Vai |
| 2002 |
TAZZA mock-up pebble beds. Experimental and theoretical investigations |
eedings |
Vai |
| 2002 |
Studio termomeccanico del modulo Limiter del reattore ITER-FEAT |
Monografia |
Vai |
| 2002 |
Fusion pebble bed thermo-mechanical modelling. Status of the research activity at the DIN |
Monografia |
Vai |
| 2002 |
Fusion pebble bed thermo-mechanical modelling. Final report B. Coupled thermo-mechanical analyses in presence of volumetric heat sources |
Monografia |
Vai |
| 2002 |
Thermal tests of ceramic breeder pebble beds for the Helium Cooled (HCPB) DEMO blanket |
eedings |
Vai |
| 2002 |
Studio della risposta nucleare del Water-Cooled Lithium Lead Test Blanket Module nel reattore ITER-FEAT |
Monografia |
Vai |
| 2002 |
On the thermal conductivity of a single size beryllium pebble bed |
eedings |
Vai |
| 2002 |
Fusion pebble bed thermo-mechanical modelling. Final report A. Status of the research activity at the DIN |
Monografia |
Vai |
| 2002 |
Fusion pebble bed thermo-mechanical modelling. Final report C. Uncoupled thermo-mechanical analyses with creep models |
Monografia |
Vai |
| 2002 |
TAZZA test section. Status of the research activity at the DIN |
Monografia |
Vai |
| 2001 |
The Iter Divertor Vertical Target Dummy Armor Prototype. Theoretical and Experimental Thermal-hydraulic and Thermo-mechanical Study |
eedings |
Vai |
| 2001 |
Modelling of the thermal mechanical behaviour of a single size beryllium pebble bed |
Articolo in rivista |
Vai |
| 2000 |
The thermoelasticity problem of axisymmetric solids with a thermal conductivity linearly depending on the temperature and on the volumetric strain |
Monografia |
Vai |
| 2000 |
On the use of the Porous Elasticity and the Drucker-Prager models in the numerical simulations of the pebble beds thermo-mechanical behavior |
eedings |
Vai |
| 2000 |
Study of a Water-Cooled Convective Divertor Prototype for the DEMO Fusion Reactor |
Capitolo o Saggio |
Vai |
| 2000 |
A Thermo-Mechanical Constitutive Model of the Lithium Orthosilicate and Beryllium Pebble Beds. An Application on the Thermo-Mechanical Study of the Smarts Mock-Up of the ITER Fusion Reactor Breeding Blanket |
eedings |
Vai |
| 2000 |
Thermomechanical analyses of the DEMO-HCPB TBM medium scale mock-up to be tested in the HE-FUS3 facility |
eedings |
Vai |
| 1996 |
Thermal Parametric and Thermo-Mechanical analyses for the Limiter Blanket Module of ITER |
Monografia |
Vai |
