Sfoglia per Relatore
Numerical and experimental study of the dynamic behavior of natural circulation systems using molten salts for heat removal
2024/2025 NARVAEZ ARRUA, JONAS SEBASTIAN
One-dimensional two-phase flow drift flux model for a BWR rod bundle under conditions of low flow rate and wide range of pressures
2017/2018 PASCAI, ENRICO
A Physics Study on Moderated SiC Blocks for High-Temperature Gas-cooled Reactors
2023/2024 BAZZANI, DAVIDE
A physics-based model of the EU 1MW 170GHz Gyrotron's MIG for control system design.
2021/2022 Bertazzoni, Ruggero Guido
Predizione di instabilità termoidrauliche in canali dritti ed elicoidali mediante codice RELAP5
2009/2010 MILLEFANTI, MIRKO
Preliminary analysis of the MSRE dynamic behaviour
2009/2010 SPINELLI, BENEDETTO MARIA
Preliminary design, modelling and simulation of intermediate loop and energy conversion system for the molten salt fast reactor
2016/2017 DI RONCO, ANDREA
Reduced basis methods for data assimilation in real thermal hydraulics systems
2020/2021 Riva, Stefano
Reduced order methods: applications to nuclear reactor core spatial dynamics
SARTORI, ALBERTO
Safety parameters uncertainty and sensitivity analysis for the high flux reactor of Institut Laue-Langevin
2018/2019 PORTINARI, DAVIDE
Shadowing effect correction for the Pavia TRIGA reactor using Monte Carlo data and reduced-order modelling techniques
2023/2024 DE LURION DE L'ÉGOUTHAIL, CYRILLE GHISLAIN BENOIT MARIE
Single and parallel channel stability analysis by means of multiphysics modeling
2009/2010 GIORGI, GIANLUCA
Sodium Fast Reactor Core Design
2023/2024 Diana, Emanuele
Stability analysis of density wave oscillations with application to BRW and SCWR nuclear reactors
2015/2016 CERVI, ERIC
Stability analysis of natural circulation loops with internally heated fluid
2014/2015 CAUZZI, MARCO TUDOR
Stability and sensitivity analysis for compressible fluids in MHD problems
2019/2020 PASTORE, FRANCESCO
Studio della produzione di plutonio protetto tramite il drogaggio di attinidi minori nel combustibile nucleare
2012/2013 FERRERI, DANIELE
Study on the effects of geometry on laminar flow in helical coiled pipes
2011/2012 DE AMICIS, JACOPO
A subchannel thermal-hydraulic analysis of the 250 kW TRIGA nuclear reactor
2019/2020 CASTELLI, DAVIDE
Survey of two phase pressure drops correlations : verifications, comparisons, improvements
2011/2012 FAIMALI, ELISA
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