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Titolo Data di pubblicazione Autori File
A Model Predictive Control Approach for the Italian LBE-XADS 1-gen-2008 CAMMI, ANTONIOCASELLA, FRANCESCOLUZZI, LELIORICOTTI, MARCO ENRICO +
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
Thoria and Inert Matrix Fuels for a Sustainable Nuclear Power 1-gen-2008 LUZZI, LELIOPADOVANI, ENRICO +
Simulation of Power Ramp Tested LWR Fuel Rods by means of the TRANSURANUS Code 1-gen-2009 PASTORE, GIOVANNIBOTAZZOLI, PIETRODI MARCELLO, VALENTINOLUZZI, LELIO
Assessment of COMSOL Capabilities to Analyse the Thermo-Hydrodynamic Behaviour of the MSR Core 1-gen-2009 CAMMI, ANTONIODI MARCELLO, VALENTINOLUZZI, LELIO +
Innovative Techniques for the Simulation and Control of Nuclear Power Plants 1-gen-2009 CAMMI, ANTONIOLUZZI, LELIO
Applying Advanced Neutron Transport Calculation for Improving Fuel Performance Codes 1-gen-2009 BOTAZZOLI, PIETROLUZZI, 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 +
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 Approach to the Dynamic Behaviour of Circulating Fuel Reactors for Generation IV 1-gen-2009 DI MARCELLO, VALENTINOCAMMI, ANTONIOLUZZI, LELIO
A Numerical Assessment of the Load Bearing Capacity of Thick Tubes Pressurized from Outside 1-gen-2009 LUZZI, LELIO +
Extension of the TRANSURANUS Code to the Fuel Rod Performance Analysis of LBE-Cooled Nuclear Reactors 1-gen-2009 BOTAZZOLI, PIETRODI MARCELLO, VALENTINOLUZZI, LELIO +
Assessment of the Prediction Capability of the TRANSURANUS Fuel Performance Code on the Basis of Power Ramp Tested LWR Fuel Rods 1-gen-2010 PASTORE, GIOVANNIBOTAZZOLI, PIETRODI MARCELLO, VALENTINOLUZZI, LELIO
Development of a Simulation Tool for a Preliminary Analysis of the MSR Core Dynamics 1-gen-2010 FIORINA, CARLOCAMMI, ANTONIOGUERRIERI, CLAUDIA RENATALUZZI, LELIO +
A Preliminary Approach to the Extension of the TRANSURANUS Code to the Fuel Rod Performance Analysis of HLM-Cooled Nuclear Reactors 1-gen-2010 LUZZI, LELIOBOTAZZOLI, PIETROPASTORE, GIOVANNI +
A Multi-Physics Numerical Model for the MSR Core Dynamics 1-gen-2010 GUERRIERI, CLAUDIA RENATACAMMI, ANTONIOFIORINA, CARLOLUZZI, LELIO
A Generalized Approach to Heat Transfer in Pipe Flow with Internal Heat Generation 1-gen-2010 DI MARCELLO, VALENTINOCAMMI, ANTONIOLUZZI, LELIO
An Approach for the Modelling and the Analysis of the MSR Thermo-Hydrodynamic Behaviour 1-gen-2010 LUZZI, LELIOCAMMI, ANTONIODI MARCELLO, VALENTINOFIORINA, CARLO
Mostrati risultati da 41 a 60 di 220
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