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PIETRO ALESSANDRO DI MAIO

Curriculum and Research

DI MAIO PIETRO ALESSANDRO

PIETRO ALESSANDRO DI MAIO

 (IIND-07/D)

Ingegneria

Contacts

+3909123897355

pietroalessandro.dimaio@unipa.it

Download the curriculum in pdf file

Subjects

Academic Year Subject identification code Subject name ECTS Course of study
2024/2025 23141 NUCLEAR FUSION REACTORS 6 INGEGNERIA ENERGETICA E NUCLEARE
2024/2025 05771 PRINCIPI DI INGEGNERIA NUCLEARE 9 INGEGNERIA DELL'ENERGIA E DELLE FONTI RINNOVABILI
2024/2025 07544 TERMOIDRAULICA 9 INGEGNERIA DELL'ENERGIA E DELLE FONTI RINNOVABILI

Publications

Date Title Type Record
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 Go to
2023 ADRANOS: A numerical tool developed to analyse coolant operating conditions of the EU-DEMO divertor Articolo in rivista Go to
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 Go to
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 Go to
2023 Thermal-hydraulic study of the Primary Heat Transport System of the DEMO Divertor Cassette Body Articolo in rivista Go to
2023 Design and Integration of the EU-DEMO Water-Cooled Lead Lithium Breeding Blanket Articolo in rivista Go to
2023 Thermofluid-dynamic assessment of the EU-DEMO divertor single-circuit cooling option Articolo in rivista Go to
2023 Study of the thermo-mechanical performances of the EU-DEMO Water-Cooled Lead Lithium Left Outboard Blanket segment Articolo in rivista Go to
2023 Exploratory study of the EU-DEMO Water-Cooled Lithium Lead breeding blanket behaviour in case of loss of cooling capability Articolo in rivista Go to
2023 Structural assessment of the EU-DEMO water-cooled lead lithium central outboard blanket segment adopting the sub-modelling technique Articolo in rivista Go to
2023 Current status of MELCOR 2.2 for fusion safety analyses Articolo in rivista Go to
2023 Development of a thermal-hydraulic model of the EU-DEMO Water Cooled Lithium Lead Breeding Blanket Primary Heat Transport System Articolo in rivista Go to
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 Go to
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 Go to
2022 Tokamak cooling systems and power conversion system options Articolo in rivista Go to
2022 A Numerical Approach to Study Shell-Side Fluid Flow in Shell-and-Tube Heat Exchangers Articolo in rivista Go to
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 Go to
2022 Divertor of the European DEMO: Engineering and technologies for power exhaust Articolo in rivista Go to
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 Go to
2022 Cold Leg LBLOCA uncertainty analysis using TRACE/DAKOTA coupling Articolo in rivista Go to
2022 Special Issue on Structural and Thermo-Mechanical Analyses in Nuclear Fusion Reactors Nota o commento Go to
2022 On the modelling of tritium transport phenomena at fluid-structure interfaces Articolo in rivista Go to
2022 Production and transport modelling of Po-210 in DEMO reactor Articolo in rivista Go to
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 Go to
2021 Determination of a pre-heating sequence for the DONES Target Assembly Articolo in rivista Go to
2021 Conceptual design of the main Ancillary Systems of the ITER Water Cooled Lithium Lead Test Blanket System Articolo in rivista Go to
2021 Hydraulic characterization of the full scale mock-up of the demo divertor outer vertical target Articolo in rivista Go to
2021 The demo water-cooled lead–lithium breeding blanket: Design status at the end of the pre-conceptual design phase Articolo in rivista Go to
2021 Hydraulic assessment of an upgraded pipework arrangement for the DEMO divertor plasma facing components cooling circuit Articolo in rivista Go to
2021 Structural assessment of a whole toroidal sector of the HELIAS 5-B breeding blanket Articolo in rivista Go to
2021 Thermal-hydraulic study of the DEMO divertor cassette body cooling circuit equipped with a liner and two reflector plates Articolo in rivista Go to
2021 Pre-conceptual design of EU-DEMO divertor primary heat transfer systems Articolo in rivista Go to
2021 Multiphysics Optimization for First Wall Design Enhancement in Water-Cooled Breeding Blankets Articolo in rivista Go to
2021 Structural assessment of the EU-DEMO WCLL Central Outboard Blanket segment under normal and off-normal operating conditions Articolo in rivista Go to
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 Go to
2020 Preliminary design of the top cap of DEMO Water-Cooled Lithium Lead breeding blanket segments Articolo in rivista Go to
2020 Assessment of Fatigue Effects Induced by Fast Beam Transients in the IFMIF-DONES Li Target Articolo in rivista Go to
2020 Progress of the conceptual design of the European DEMO breeding blanket, tritium extraction and coolant purification systems Articolo in rivista Go to
2020 Parametric study of the influence of double-walled tubes layout on the DEMO WCLL breeding blanket thermal performances Articolo in rivista Go to
2020 On the impact of the heat transfer modelling approach on the prediction of EU-DEMO WCLL breeding blanket thermal performances Articolo in rivista Go to
2020 On the thermal-hydraulic performances of the DEMO divertor cassette body cooling circuit equipped with a liner Articolo in rivista Go to
2020 Assessment of DEMO WCLL breeding blanket primary heat transfer system isolation valve absorbed doses due to activated water Articolo in rivista Go to
2020 Safety analysis of the DONES primary heat removal system Articolo in rivista Go to
2020 Analytical and Numerical Assessment of Thermally Induced Pressure Waves in the IFMIF-DONES Liquid-Lithium Target Articolo in rivista Go to
2020 On the numerical assessment of the thermal-hydraulic operating map of the DEMO Divertor Plasma Facing Components cooling circuit Articolo in rivista Go to
2020 Investigation of the DEMO WCLL Breeding Blanket Cooling Water Activation Articolo in rivista Go to
2020 Eurofusion-DEMO Divertor - Cassette Design and Integration Articolo in rivista Go to
2019 Further improvements in the structural analysis of DEMO Divertor Cassette body and design assessment according to RCC-MRx Articolo in rivista Go to
2019 Conceptual design of the enhanced coolant purification systems for the European HCLL and HCPB test blanket modules Articolo in rivista Go to
2019 On the effect of stiffening plates configuration on the DEMO Water Cooled Lithium Lead Breeding Blanket module thermo-mechanical behaviour Articolo in rivista Go to
2019 Updated design and integration of the ancillary circuits for the European Test Blanket Systems Articolo in rivista Go to
2019 Thermal-hydraulic optimisation of the DEMO divertor cassette body cooling circuit equipped with a liner Articolo in rivista Go to
2019 On the thermal dynamic behaviour of the helium-cooled DEMO fusion reactor Articolo in rivista Go to
2019 The design of the DONES lithium target system Articolo in rivista Go to
2019 Progress in the design development of EU DEMO helium-cooled pebble bed primary heat transfer system Articolo in rivista Go to
2019 Parametric study of the influence of First Wall cooling water on the Water Cooled Lithium Lead Breeding Blanket nuclear response Articolo in rivista Go to
2019 Structural verification and manufacturing procedures of the cooling system, for DEMO divertor target (OVT) Articolo in rivista Go to
2019 Thermal-hydraulic and thermo-mechanical simulations of Water-Heavy Liquid Metal interactions towards the DEMO WCLL breeding blanket design Articolo in rivista Go to
2019 Recent progress in developing a feasible and integrated conceptual design of the WCLL BB in EUROfusion project Articolo in rivista Go to
2019 Validation of Multi-Physics Integrated Procedure for the HCPB Breeding Blanket Articolo in rivista Go to
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 Go to
2019 A multi-physics integrated approach to breeding blanket modelling and design Articolo in rivista Go to
2019 On the effects of the Double-Walled Tubes lay-out on the DEMO WCLL breeding blanket module thermal behavior Articolo in rivista Go to
2019 Hydraulic analysis of EU-DEMO divertor plasma facing components cooling circuit under nominal operating scenarios Articolo in rivista Go to
2018 Development of a Two-Dimensional Simplified Tool for the Analysis of the Cooling of the ITER TF Winding Pack Articolo in rivista Go to
2018 Advancements in DEMO WCLL breeding blanket design and integration Articolo in rivista Go to
2018 On the thermal-hydraulic optimization of DEMO divertor plasma facing components cooling circuit Articolo in rivista Go to
2018 Multi-Module vs. Single-Module concept: Comparison of thermomechanical performances for the DEMO Water-Cooled Lithium Lead breeding blanket Articolo in rivista Go to
2018 On the thermal and thermomechanical assessment of the “Optimized Conservative” helium-cooled lithium lead breeding blanket concept for DEMO Articolo in rivista Go to
2018 Progress in EU Breeding Blanket design and integration Articolo in rivista Go to
2018 Thermomechanical analysis supporting the preliminary engineering design of DONES target assembly Articolo in rivista Go to
2018 Computational thermofluid-dynamic analysis of DEMO divertor cassette body cooling circuit Articolo in rivista Go to
2018 Preliminary design of EU DEMO helium-cooled breeding blanket primary heat transfer system Articolo in rivista Go to
2018 Recent Progress in the WCLL Breeding Blanket Design for the DEMO Fusion Reactor Articolo in rivista Go to
2018 Numerical assessment of the thermomechanical behaviour of the DEMO Water-Cooled Lithium Lead inboard blanket equatorial module Articolo in rivista Go to
2017 Assessment of the importance of neutron multiplication for tritium production Articolo in rivista Go to
2017 Thermo-mechanical analysis of irradiation swelling and design optimization of the IFMIF target assembly with bayonet backplate Articolo in rivista Go to
2017 WCLL breeding blanket design and integration for DEMO 2015: status and perspectives Articolo in rivista Go to
2017 On the thermo-mechanical behaviour of DEMO water-cooled lithium lead equatorial outboard blanket module Articolo in rivista Go to
2017 Structural analysis of the back supporting structure of the DEMO WCLL outboard blanket Articolo in rivista Go to
2017 Progress in the initial design activities for the European DEMO divertor: Subproject "Cassette" Articolo in rivista Go to
2017 Analysis of steady state thermal-hydraulic behaviour of the DEMO divertor cassette body cooling circuit Articolo in rivista Go to
2017 Thermal-hydraulic behaviour of the DEMO divertor plasma facing components cooling circuit Articolo in rivista Go to
2017 Thermal optimization of the Helium-Cooled Lithium Lead breeding zone layout design regarding TBR enhancement Articolo in rivista Go to
2016 On the optimization of the first wall of the DEMO water-cooled lithium lead outboard breeding blanket equatorial module Articolo in rivista Go to
2016 Draining and drying process development of the Tokamak Cooling Water System of ITER Articolo in rivista Go to
2016 Design and manufacturing feasibility of ITER TBM Frame and Dummy TBMs Articolo in rivista Go to
2016 Optimization of the breeder zone cooling tubes of the DEMO Water-Cooled Lithium Lead breeding blanket Articolo in rivista Go to
2016 First Flight Escape Probability and Uncollided Flux of Nuclear Particles in Convex Bodies with Spherical Symmetry Articolo in rivista Go to
2016 On the hydraulic behaviour of ITER Shield Blocks #14 and #08. Computational analysis and comparison with experimental tests Articolo in rivista Go to
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 Go to
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 Go to
2015 Analysis of the steady state hydraulic behaviour of the ITER blanket cooling system Articolo in rivista Go to
2015 Analysis of the thermomechanical behavior of the IFMIF bayonet target assembly under design loading scenarios Articolo in rivista Go to
2015 Optimization of the first wall for the DEMO water cooled lithium lead blanket Articolo in rivista Go to
2015 Numerical simulation of the transient thermal-hydraulic behaviour of the ITER blanket cooling system under the draining operational procedure Articolo in rivista Go to
2014 Hydraulic Analysis of Blanket Cooling System Monografia Go to
2014 Status of ITER TBM port plug conceptual design and analyses Articolo in rivista Go to
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 Proceedings Go to
2014 Analysis of the steady state thermal-hydraulic behaviour of the ITER blanket cooling system Proceedings Go to
2014 Optimization of the First Wall for the DEMO Water Cooled Lithium Lead Blanket Proceedings Go to
2014 Steady state thermo-mechanical analysis of the IFMIF Lithium target system with bayonet backplate under design conditions Proceedings Go to
2014 Start-up and shutdown thermomechanical transient analyses of the IFMIF European lithium target system Articolo in rivista Go to
2014 Analysis of the thermo-mechanical behaviour of the DEMO Water-Cooled Lithium Lead breeding blanket module under normal operation steady state conditions Proceedings Go to
2014 Numerical simulation of the transient thermal-hydraulic behaviour of the ITER blanket cooling system under the draining operational procedure Proceedings Go to
2014 Hydraulic Analysis of Blanket Cooling System Monografia Go to
2014 Analysis of the thermo-mechanical behaviour of IFMIF target assembly integrated with its support framework Monografia Go to
2014 On the numerical assessment of the thermo-mechanical performances of the DEMO Helium-Cooled Pebble Bed breeding blanket module Articolo in rivista Go to
2013 Analysis of the thermo-mechanical behaviour of IFMIF fast disconnecting system Monografia Go to
2013 Fattibilità di una diversa configurazione della facility SPES-3 Monografia Go to
2013 Analysis of a Generation 3+ Pressurised Water Reactor plant response to a postulated Station Black Out Proceedings Go to
2013 Analysis of the thermo-mechanical behaviour of IFMIF target assembly Monografia Go to
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 Go to
2013 Engineering design and steady state thermomechanical analysis of the IFMIF European lithium target system Proceedings Go to
2013 Water Cooled First Wall optimization for WCLL DEMO reactor Monografia Go to
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 Go to
2013 The European contribution to the development and validation activities for the design of IFMIF lithium facility Articolo in rivista Go to
2013 Design, manufacturing and testing of a fast disconnecting system for the European target assembly concept of IFMIF Proceedings Go to
2013 Hydraulic Analysis of Blanket Cooling System Monografia Go to
2013 Nuclear Analysis of an ITER Blanket Module Articolo in rivista Go to
2013 Preliminary design of a Water Cooled Lithium Lead blanket concept for DEMO reactor Monografia Go to
2013 Hydraulic Analysis of the CDR Design of the ITER TBM Port Plug Monografia Go to
2012 Thermal-hydraulic and thermal-structural analyses report of DEMO Helium-Cooled Pebble Bed blanket Monografia Go to
2012 Adeguamento dello SPES2 per Prove di Sicurezza. Analisi Preliminari per La Simulazione di un Incidente Tipo Fukushima su SPES-2 Monografia Go to
2012 Study of the thermo-mechanical performances of the IFMIF-EVEDA Lithium Test Loop target assembly Articolo in rivista Go to
2012 On the investigation of Lithium Methatitanate pebble bed thermal diffusive properties by the Improved Current Pulse method Proceedings Go to
2012 Status of ceramic breeder pebble bed thermo-mechanics R&D and impact on breeder material mechanical strength Articolo in rivista Go to
2012 Thermal-hydraulic and thermal-structural analyses report of DEMO WCLL blanket Monografia Go to
2012 Analysis of the thermo-mechanical behaviour of IFMIF Target Assembly Monografia Go to
2012 On the Improved Current Pulse method for the thermal diffusive characterization of lithiated ceramic pebble beds Articolo in rivista Go to
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 Go to
2012 A neutron point kinetic model for fusion relevant calculations Articolo in rivista Go to
2011 A Training Experience of Operators with the AGN-201 “Costanza” Research Reactor of Palermo University Proceedings Go to
2011 Electrical Aging Tests on Enameled Wire Exposed to Gamma Irradiation Proceedings Go to
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 Go to
2011 PROVE ED ESPERIMENTI DI VERIFICA DELLA SICUREZZA DEL REATTORE NUCLEARE DI RICERCA AGN-201 “COSTANZA” Articolo in rivista Go to
2011 Analysis of the SPES-3 direct vessel injection line break by using TRACE code Proceedings Go to
2011 Thermo-mechanical issues induced by neutron swelling in the IFMIF Target Assembly back-plate Monografia Go to
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 Go to
2011 On thermo-mechanical issues induced by irradiation swelling inside the back-plate of the IFMIF target assembly Articolo in rivista Go to
2011 Hydraulic characterization of the full scale divertor cassette prototype Articolo in rivista Go to
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 Go to
2011 On the computational assessment of the IFMIF-EVEDA Target Assembly thermal behaviour Proceedings Go to
2011 Analysis of the thermo-mechanical behaviour of IFMIF-EVEDA Lithium Test Loop Target Assembly Monografia Go to
2010 TRACE input model for SPES3 facility Monografia Go to
2010 Education and Research in Nuclear Engineering and Radiological Protection at Nuclear Engineering Department of Palermo University Proceedings Go to
2010 Applicazione del metodo Monte Carlo a problemi monodimensionali di conduzione termica stazionaria in sistemi con conducibilità dipendente dalla posizione Articolo in rivista Go to
2010 On the theoretical–numerical study of the HEXCALIBER mock-up thermo-mechanical behaviour Articolo in rivista Go to
2010 Modifiche del Codice RELAP5 per lo Studio delle Perdite di Carico in Generatori di Vapore a Tubi Elicoidali Interessati da Flussi Bifase Monografia Go to
2010 On the hyperporous non-linear elasticity model for fusion-relevant pebble beds Articolo in rivista Go to
2010 ITER Upper Port Plug Draining and Drying Monografia Go to
2010 Thermal-mechanical and thermal-hydraulic integrated study of the Helium-Cooled Lithium Lead Test Blanket Module Articolo in rivista Go to
2010 On the improved current pulse method for the thermal diffusive characterization of lithiated ceramic pebble beds Proceedings Go to
2010 On the numerical assessment of the thermal-hydraulic behaviour of ITER Upper Port Plug Main Body cooling circuit Proceedings Go to
2009 Assessment of the Possible Lay-Out Influence on the HCLL-TBM Nuclear Response Articolo in rivista Go to
2009 HEXCALIBER TEST SECTION. Thermo-mechanical analysis Monografia Go to
2009 On the improved current pulse method for the dynamic assessment of thermal diffusive properties Articolo in rivista Go to
2009 Thermal analysis of the Helium-Cooled Lithium Lead Test Blanket Module to be irradiated in ITER Proceedings Go to
2009 On a computational study of the hydraulic behavior of the ITER divertor cassette full-scale prototype Proceedings Go to
2009 The hydraulic behaviour of the prototype of on a ITER divertor cassette Monografia Go to
2009 Study of the helium-cooled lithium lead test blanket module nuclear behaviour under irradiation in ITER Articolo in rivista Go to
2008 Experimental tests and thermo-mechanical analyses on the HEXCALIBER mock-up Articolo in rivista Go to
2008 A Monte Carlo study on the possible lay-out influence in the HCLL-TBM nuclear response Proceedings Go to
2008 Steady state and transient thermal-hydraulic characterization of full-scale ITER divertor plasma facing components Articolo in rivista Go to
2008 A study of the potential influence of frame coolant distribution on the radiation-induced damage of HCLL-TBM structural material Articolo in rivista Go to
2008 Thermo-mechanical experiment and analysis on an HCPB-TBM mock-up Proceedings Go to
2008 XXVI Congresso Nazionale sulla Trasmissione del Calore Curatela Go to
2008 On the numerical and experimental characterisation of the ITER divertor cassette plasma facing component steady state hydraulic behaviour Proceedings Go to
2008 On the assessment of lithium orthosilicate pebble bed thermal diffusive properties by the improved current pulse method Proceedings Go to
2007 The hydraulic behaviour of the simulacrum of the Inner Vertical Target of an ITER divertor cassette Monografia Go to
2007 Studies on the AGN - 201 "COSTANZA" Research Reactor Proceedings Go to
2007 The hydraulic behaviour of the simulacrum of the Outer Vertical Target of an ITER divertor cassette Monografia Go to
2007 A study of the potential influence of frame coolant on HCLL-TBM nuclear response Articolo in rivista Go to
2007 The hydraulic behaviour of the simulacrum of the Dome Liner of an ITER divertor cassette Monografia Go to
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 Go to
2007 On the effects of the supporting frame on the radiation-induced damage of HCLL-TBM structural material Articolo in rivista Go to
2007 HEXCALIBER TEST SECTION. Preliminary thermo-mechanical analysis Monografia Go to
2007 The hydraulic behaviour of the simulacrum of a Plasma Vessel Module of the W 7-X Reactor Monografia Go to
2006 Preparation of HEXCALIBER tests and preliminary thermo-mechanical analyses Proceedings Go to
2006 The HELICA mock-up. Experimental results and numerical thermo-mechanical analyses Proceedings Go to
2006 Mixed MHD Convection and Tritium Transport in HCLL TBM Breeder Units for the ITER Fusion Reactor Proceedings Go to
2006 Progress in the benchmark exercise for analyzing the lithiate breeder pebble bed thermo-mechanical behaviour Articolo in rivista Go to
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 Go to
2006 Piano di emergenza per il reattore nucleare di ricerca AGN-201 COSTANZA dell’Università di Palermo: presupposti tecnici e valutazioni radiologiche Proceedings Go to
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 Proceedings Go to
2005 Sezione di prova HELICA. Analisi termomeccaniche Monografia Go to
2005 On the AGN - 201 "COSTANZA" Research Reactor at the Department of Nuclear Engineering of the University of Palermo Proceedings Go to
2005 Out of Pile Thermo-Mechanical Testing of Breeder Pebble Beds for HCPB TBM for ITER Proceedings Go to
2005 Mixed MHD convection and Tritium transport in fusion-relevant configurations Articolo in rivista Go to
2005 Steady-state and transient thermal-hydraulic analyses on ITER divertor module Articolo in rivista Go to
2005 On the nuclear response of the helium-cooled lithium lead test blanket module in ITER Articolo in rivista Go to
2005 On the effects of the supporting frame on the radiation-induced damage of HCLL-TBM structural material Proceedings Go to
2005 On the use of an improved current pulse method for the experimental determination of the thermal diffusive properties of packed pebble beds Proceedings Go to
2005 Final report on the test campaigns HELICA I-II performed in HEFUS facility Monografia Go to
2005 The ITER divertor cassette. Steady-state characterisation and draining and drying transient hydraulic analyses Proceedings Go to
2004 Final report on the contract EFDA 682 - Preparation of integration and hydraulic tests of full-scale divertor components. Monografia Go to
2004 Steady state and transient thermal-hydraulic analyses on ITER divertor cassette Proceedings Go to
2004 Mixed magnetohydrodynamic convection in poloidal Helium-Cooled Lithium Lead blanket modules of a fusion reactor Proceedings Go to
2004 The hydraulic behaviour of the ITER full-scale divertor cassette. The steady state analyses Monografia Go to
2004 The hydraulic behaviour of the ITER full-scale divertor cassette. The transient analyses Monografia Go to
2004 Thermo-mechanical testing of Li-ceramic for the helium cooled pebble bed (HCPB) breeding blanket Articolo in rivista Go to
2003 Studio del comportamento termico di letti di sfere tramite il metodo dell’impulso di corrente Monografia Go to
2003 A Semi-Theoretical Approach to a Correlation for the Thermal Conductivity of a Beryllium Pebble Bed Articolo in rivista Go to
2003 On the nuclear response of the HCLL-TBM in ITER-FEAT Monografia Go to
2003 MHD Free Convection in Helium-Cooled Lithium-Lead Blanket Modules for the Demonstration Fusion Reactor Proceedings Go to
2003 Experimental tests on Li-ceramic breeders for the helium cooled pebble bed (HCPB) blanket design Articolo in rivista Go to
2003 On the nuclear impact of different coolants in the HCLL-TBM in ITER-FEAT Monografia Go to
2003 La sezione di prova HELICHETTA. Analisi termomeccaniche numeriche e sperimentali Monografia Go to
2003 On the nuclear response of the water-cooled Pb-17Li test blanket module for ITER-FEAT Articolo in rivista Go to
2003 Experimental investigations on the thermal conductivity of packed pebble beds by the current pulse method Proceedings Go to
2002 TAZZA test section. Status of the research activity at the DIN Monografia Go to
2002 Studio della risposta nucleare del Water-Cooled Lithium Lead Test Blanket Module nel reattore ITER-FEAT Monografia Go to
2002 On the thermal conductivity of a single size beryllium pebble bed Proceedings Go to
2002 Fusion pebble bed thermo-mechanical modelling. Final report A. Status of the research activity at the DIN Monografia Go to
2002 Fusion pebble bed thermo-mechanical modelling. Final report C. Uncoupled thermo-mechanical analyses with creep models Monografia Go to
2002 Thermal tests of ceramic breeder pebble beds for the Helium Cooled (HCPB) DEMO blanket Proceedings Go to
2002 Neutronic and photonic analysis of the water-cooled Pb-17Li test blanket module for ITER-FEAT Articolo in rivista Go to
2002 TAZZA mock-up pebble beds. Experimental and theoretical investigations Proceedings Go to
2002 Studio termomeccanico del modulo Limiter del reattore ITER-FEAT Monografia Go to
2002 Fusion pebble bed thermo-mechanical modelling. Status of the research activity at the DIN Monografia Go to
2002 Fusion pebble bed thermo-mechanical modelling. Final report B. Coupled thermo-mechanical analyses in presence of volumetric heat sources Monografia Go to
2001 Modelling of the thermal mechanical behaviour of a single size beryllium pebble bed Articolo in rivista Go to
2001 The Iter Divertor Vertical Target Dummy Armor Prototype. Theoretical and Experimental Thermal-hydraulic and Thermo-mechanical Study Proceedings Go to
2000 Thermomechanical analyses of the DEMO-HCPB TBM medium scale mock-up to be tested in the HE-FUS3 facility Proceedings Go to
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 Proceedings Go to
2000 Study of a Water-Cooled Convective Divertor Prototype for the DEMO Fusion Reactor Capitolo o Saggio Go to
2000 The thermoelasticity problem of axisymmetric solids with a thermal conductivity linearly depending on the temperature and on the volumetric strain Monografia Go to
2000 On the use of the Porous Elasticity and the Drucker-Prager models in the numerical simulations of the pebble beds thermo-mechanical behavior Proceedings Go to
1996 Thermal Parametric and Thermo-Mechanical analyses for the Limiter Blanket Module of ITER Monografia Go to