RE.PUBLIC@POLIMI pubblicazioni di ricerca del Politecnico di Milano

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Resistenza alla Propagazione di Cricche per l’Acciaio da Vessel Nucleare in Ambiente LWR 1-gen-1994 LUZZI, LELIO +
Prove di Tenacità a Frattura: Metodo Sperimentale ed Elaborazione dei Dati 1-gen-1994 LUZZI, LELIO +
Inert Matrix and Thoria Fuels for Plutonium Burning in LWRs 1-gen-1998 LUZZI, LELIOPADOVANI, ENRICORICOTTI, MARCO ENRICO +
A Thermoelastic Method for Thermal Diffusivity Measurements on Solids 1-gen-1999 BEGHI, MARCOLUZZI, LELIO
Innovative Inert Matrix-Thoria Fuels for in-Reactor Plutonium Disposition 1-gen-1999 PADOVANI, ENRICOLUZZI, LELIO +
Preliminary Fabrication and Characterisation of Inert Matrix and Thoria Fuels for Plutonium Disposition in Light Water Reactors 1-gen-1999 LUZZI, LELIOOSSI, PAOLO MARIA +
A Thermoelastic Method for Measuring the Thermal Diffusivity of Solids 1-gen-1999 BEGHI, MARCOLUZZI, LELIO
Feasibility of Advanced Fuel or Target Fabrication 1-gen-2000 LUZZI, LELIO +
Dispositivo per la misura di proprietà termofisiche dei solidi e procedimento di misura relativo - Brevetto per invenzione industriale N. 01302183, luglio 2000Estensione europea: Device for Measuring Thermophysical Properties of Solid Materials and Method Therefore 1-gen-2000 BEGHI, MARCOLUZZI, LELIO
Thermal contact resistance calibration for thermal diffusivity measurement of metals by the thermoelastic method 1-gen-2000 BEGHI, MARCOLUZZI, LELIO
A thermoelastic method for the measurement of thermal expansion coefficient of solids 1-gen-2000 BEGHI, MARCOLUZZI, LELIO
ADS-demo Fuel Rod Analysis Report 1-gen-2001 LUZZI, LELIO +
A multiproperty method and apparatus for thermophysical measurements on solids 1-gen-2001 BEGHI, MARCOLUZZI, LELIO
Inert matrix and thoria fuels for plutonium elimination 1-gen-2001 LOMBARDI, CARLOLUZZI, LELIOPADOVANI, ENRICO +
Validation of TRANSURANUS Code on the basis of the Studsvik Super-Ramp PWR Database Files 1-gen-2002 LUZZI, LELIO
TRANSURANUS Code Implementation at ENEA 1-gen-2002 LUZZI, LELIO +
ADS-Demo Fuel Rod Analysis 1-gen-2003 LUZZI, LELIO +
Thermal Hydraulic Analysis of IRIS Reactor Coiled Tube Steam Generator 1-gen-2003 CAMMI, ANTONIOLUZZI, LELIORICOTTI, MARCO ENRICO +
Preliminary Thermo-Mechanical Analyses of IRIS Steam Generator Tube 1-gen-2003 LUZZI, LELIO
Thermophysical characterization of elastic solids : a novel application for the material testing machine 1-gen-2003 BEGHI, MARCOLUZZI, LELIO
ADS-Demo Fuel Rod Performance: Multivariate Statistical Analysis 1-gen-2004 LUZZI, LELIO +
Collapse of Thick Cylinders under Radial Pressure and Axial Load 1-gen-2005 LUZZI, LELIO +
Plasticity-instability coupling effects on the collapse of thick tubes 1-gen-2005 CORRADI DELL'ACQUA, LEONE MARIALUZZI, LELIO +
LBE-XADS Fuel Rod Performance: Steady State and Transient Analysis 1-gen-2005 LUZZI, LELIO +
Plasticity-Instability Coupling in the Ultimate Behavior of Thick and Medium Thick Shells 1-gen-2006 CORRADI DELL'ACQUA, LEONE MARIALUZZI, LELIO +
Un problema statico relativo a reattori nucleari di nuova generazione 1-gen-2006 CORRADI DELL'ACQUA, LEONE MARIALUZZI, LELIO
Finite element limit analysis of anisotropic structures 1-gen-2006 CORRADI DELL'ACQUA, LEONE MARIALUZZI, LELIOVENA, PASQUALE
Modelling and Control Strategy of the Italian LBE-XADS 1-gen-2006 CAMMI, ANTONIOLUZZI, LELIOPORTA, ALESSANDRO ANTONIORICOTTI, MARCO ENRICO
Modelling of Circulating Nuclear Fuels with COMSOL Multiphysics 1-gen-2007 CAMMI, ANTONIODI MARCELLO, VALENTINOLUZZI, LELIO
Collapse of Thick Tubes Subjected to External Pressure 1-gen-2007 CORRADI DELL'ACQUA, LEONE MARIALUZZI, LELIORICOTTI, MARCO ENRICOGHIELMETTI, CHRISTIANDI MARCELLO, VALENTINO +
Heat Transfer Correlations for Liquid Metal Cooled Fast Reactors 1-gen-2007 LUZZI, LELIO +
Collapse of Thick Tubes Subjected to External Pressure: an Interpretation of Present Code Requirements 1-gen-2007 CORRADI DELL'ACQUA, LEONE MARIALUZZI, LELIO
Innovative Techniques for the Simulation and Control of Nuclear Power Plants 1-gen-2008 CAMMI, ANTONIOLUZZI, LELIO
Analysis of Coupled Dynamics of Molten Salt Reactors 1-gen-2008 DI MARCELLO, VALENTINOCAMMI, ANTONIOLUZZI, LELIO
Modelling of Pellet Cladding Interaction during Power Ramps in PWR Rods by means of TRANSURANUS Fuel Rod Analysis Code 1-gen-2008 DI MARCELLO, VALENTINOLUZZI, LELIO
Analysis of Thermal-Hydraulic Behaviour of the Molten Salt Nuclear Fuel 1-gen-2008 DI MARCELLO, VALENTINOCAMMI, ANTONIOLUZZI, LELIO
The Verification of the TRANSURANUS Fuel Performance Code - an Overview 1-gen-2008 LUZZI, LELIODI MARCELLO, VALENTINO +
Analysing Operational Transients by means of the TRANSURANUS Code 1-gen-2008 LUZZI, LELIODI MARCELLO, VALENTINOBOTAZZOLI, PIETRO +
Innovative Techniques for the Simulation and Control of Nuclear Power Plants 1-gen-2008 CAMMI, ANTONIOLUZZI, LELIO
Verification of TRANSURANUS Code Versions v1m1j07 and v1m1j08 against BWR Inter-Ramp Experiments 1-gen-2008 LUZZI, LELIO +
Preliminary Analysis by means of the TRANSURANUS Code of Mixed Oxide Fuel Rod for Gen IV Lead Fast Reactor 1-gen-2008 LUZZI, LELIO +
Collapse of Thick Tubes Pressurized from Outside: an Accurate Predictive Formula 1-gen-2008 CORRADI DELL'ACQUA, LEONE MARIAGHIELMETTI, CHRISTIANLUZZI, LELIO
A Model Predictive Control Approach for the Italian LBE-XADS 1-gen-2008 CAMMI, ANTONIOCASELLA, FRANCESCOLUZZI, LELIORICOTTI, MARCO ENRICO +
Thoria and Inert Matrix Fuels for a Sustainable Nuclear Power 1-gen-2008 LUZZI, LELIOPADOVANI, ENRICO +
Applying Advanced Neutron Transport Calculation for Improving Fuel Performance Codes 1-gen-2009 BOTAZZOLI, PIETROLUZZI, LELIO +
Innovative Techniques for the Simulation and Control of Nuclear Power Plants 1-gen-2009 CAMMI, ANTONIOLUZZI, LELIO
A Preliminary Approach to the Neutronics of the Molten Salt Reactor by means of COMSOL Multiphysics 1-gen-2009 MEMOLI, VITOCAMMI, ANTONIODI MARCELLO, VALENTINOLUZZI, LELIO
Extension of the TRANSURANUS Code to the Analysis of Cladding Materials for Liquid Metal Cooled Fast Reactors: a Preliminary Approach 1-gen-2009 BOTAZZOLI, PIETRODI MARCELLO, VALENTINOPASTORE, GIOVANNILUZZI, LELIO +
A Preliminary Assessment of the T91 Behaviour for the Extension of the TRANSURANUS Code to the Fuel Rod Performance Analysis of LBE Cooled Nuclear Reactors 1-gen-2009 BOTAZZOLI, PIETRODI MARCELLO, VALENTINOLUZZI, LELIOPASTORE, GIOVANNI +
Assessment of COMSOL Capabilities to Analyse the Thermo-Hydrodynamic Behaviour of the MSR Core 1-gen-2009 CAMMI, ANTONIODI MARCELLO, VALENTINOLUZZI, LELIO +
Mostrati risultati da 1 a 50 di 243
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