Sfoglia per Relatore
A burnup meta-model for application in fuel performance codes : development and verification for MOX fuel in pressurized water reactors
2017/2018 ALTIERI, STEFANO
Advancements in modelling the thermal-mechanical behaviour of MOX-fuelled pins and application to liquid-metal fast reactor conditions
2021/2022 MAGNI, ALESSIO
An innovative route for uranium carbide synthesis and densification using spark plasma sintering
2014/2015 SALVATO, DANIELE
Analysis of an Am-bearing experimental fuel pin in a MYRRHA transient scenario
2021/2022 Longoni, Luca
Application of the TRANSURANUS code to assess the MYRRHA fuel pin performance
2020/2021 Delogu, Marco
Assessment of helium intra-granular behaviour in nuclear oxide fuels
2015/2016 COGNINI, LUANA
Assessment of MYRRHA pin performance via OpenFOAM-informed TRANSURANUS simulations
2022/2023 Trombetta, Antonio
Chromia-doped UO2 fuel: engineering modeling of chromium solubility and fission gas diffusivity
2022/2023 NICODEMO, GIOVANNI
Development and application of DSC techniques for the determination of isobaric specific heat capacity in molten salt reactor fuels
2023/2024 Mariano, Andrea
Development and assessment of an open-source code for gaseous and volatile fission product behaviour in light water reactor fuel
2023/2024 Zullo, Giovanni
Development and assessment of computational fluid dynamics models for the study of natural circulation dynamics
2014/2015 FANALE, FRANCESCO
Development of a data-driven surrogate model for helium production in fast reactor Am-bearing fuels
2021/2022 KATSAMPIRIS, MARIOS-GEORGIOS
Development of a model for the corrosion of austenitic steels cladding in in lead-cooled fast reactors enviroment
2022/2023 Randazzo, Matteo
Development of MELCOR v2.2 input for the simulation of QUENCH-06 experiment
2020/2021 Garbarini, Matteo
Experimental Investigation and modelling of thermo-chemical and thermo-physical properties of fluorides for the molten salt fast reactor
2019/2020 TOSOLIN, ALBERTO
Experimental investigation of Cs-Te-O and Cs-Mo-O fission product systems
2018/2019 VOLFI, ANDREA
Experimental study of severe accident conditions in nuclear materials
2014/2015 SOLDI, LUCA
Extension and application of a fuel pin performance code in the conceptual design of a lead cooled fast reactor
2012/2013 PIZZOCRI, DAVIDE
Extension and validation of a transient fission gas release model for the TRANSURANUS fuel performance code
2014/2015 BRUSCHI, ELISA
Fission gas release during design basis accidents : surrogate and physics-based models for conventional and meso-scale nuclear fuel codes
2022/2023 PETROSILLO, GIACOMO
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