DI MARCELLO, VALENTINO

DI MARCELLO, VALENTINO  

DIPARTIMENTO DI ENERGIA  

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Titolo Data di pubblicazione Autori File
A Generalized Approach to Heat Transfer in Pipe Flow with Internal Heat Generation 1-gen-2010 DI MARCELLO, VALENTINOCAMMI, 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
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 +
An Approach for the Modelling and the Analysis of the MSR Thermo-Hydrodynamic Behaviour 1-gen-2010 LUZZI, LELIOCAMMI, ANTONIODI MARCELLO, VALENTINOFIORINA, CARLO
Analysing Operational Transients by means of the TRANSURANUS Code 1-gen-2008 LUZZI, LELIODI MARCELLO, VALENTINOBOTAZZOLI, PIETRO +
Analysis of Coupled Dynamics of Molten Salt Reactors 1-gen-2008 DI MARCELLO, VALENTINOCAMMI, ANTONIOLUZZI, LELIO
Analysis of Thermal-Hydraulic Behaviour of the Molten Salt Nuclear Fuel 1-gen-2008 DI MARCELLO, VALENTINOCAMMI, ANTONIOLUZZI, LELIO
Assessment of COMSOL Capabilities to Analyse the Thermo-Hydrodynamic Behaviour of the MSR Core 1-gen-2009 CAMMI, ANTONIODI 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
Collapse of Thick Tubes Subjected to External Pressure 1-gen-2007 CORRADI DELL'ACQUA, LEONE MARIALUZZI, LELIORICOTTI, MARCO ENRICOGHIELMETTI, CHRISTIANDI MARCELLO, VALENTINO +
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 +
Extension of the TRANSURANUS Code to the Fuel Rod Performance Analysis of LBE-Cooled Nuclear Reactors 1-gen-2009 BOTAZZOLI, PIETRODI MARCELLO, VALENTINOLUZZI, LELIO +
Modelling of Circulating Nuclear Fuels with COMSOL Multiphysics 1-gen-2007 CAMMI, ANTONIODI MARCELLO, VALENTINOLUZZI, 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
A Multi-Physics Modelling Approach to the Dynamics of Molten Salt Reactors 1-gen-2011 CAMMI, ANTONIODI MARCELLO, VALENTINOLUZZI, LELIOMEMOLI, VITORICOTTI, MARCO ENRICO
Physics-based modelling of fission gas swelling and release in UO2 applied to integral fuel rod analysis 1-gen-2013 PASTORE, GIOVANNILUZZI, LELIODI MARCELLO, VALENTINO +
A Preliminary Approach to the Dynamic Behaviour of Circulating Fuel Reactors for Generation IV 1-gen-2009 DI MARCELLO, VALENTINOCAMMI, ANTONIOLUZZI, LELIO
Simulation of Power Ramp Tested LWR Fuel Rods by means of the TRANSURANUS Code 1-gen-2009 PASTORE, GIOVANNIBOTAZZOLI, PIETRODI MARCELLO, VALENTINOLUZZI, LELIO
The Verification of the TRANSURANUS Fuel Performance Code - an Overview 1-gen-2008 LUZZI, LELIODI MARCELLO, VALENTINO +
Thermal hydraulics of liquid-fueled MSRs 1-gen-2017 LUZZI, LELIOCAMMI, ANTONIODI MARCELLO, VALENTINOPINI, ALESSANDRO