Sfoglia per Correlatore PIZZOCRI, DAVIDE
Mostrati risultati da 1 a 17 di 17
A burnup meta-model for application in fuel performance codes : development and verification for MOX fuel in pressurized water reactors
2017/2018 ALTIERI, STEFANO
Assessment of helium intra-granular behaviour in nuclear oxide fuels
2015/2016 COGNINI, LUANA
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 of a data-driven surrogate model for helium production in fast reactor Am-bearing fuels
2021/2022 KATSAMPIRIS, MARIOS-GEORGIOS
Extension and validation of a transient fission gas release model for the TRANSURANUS fuel performance code
2014/2015 BRUSCHI, ELISA
Integral validation of an intra-granular fission gas behavior model with the BISON fuel performance code
2018/2019 ROTA, GIUSEPPE
Modelling and assessment of intra-granular bubble evolution in UO2 nuclear fuel
2016/2017 MAGNI, ALESSIO
Modelling and validating fission gas release, pore migration and oxygen redistribution in MOX fuel
2018/2019 VERDOLIN, FILIPPO
Modelling dislocation density evolution in UO2 under irradiation
2023/2024 DJONOVIC, ALEKSANDAR
Modelling high burnup structure formation and evolution in SCIANTIX
2020/2021 Meleqi, Bertin
Modelling of helium behaviour in oxide nuclear fuels for fuel performance analysis
2019/2020 CECHET, ALESSANDRO
Modelling of thermal properties of minor actinide-MOX fuel and assessment against the SUPERFACT-1 irradiation experiment
2019/2020 FURÌA, ALESSIO
Multi-physics development and application of a reduced order model of fission gas diffusion in fuel performance codes
2020/2021 Di Gennaro, Martina
Numerical analysis of the effects of porosity morphology on the thermal conductivity of ceramic nuclear fuels
2024/2025 MATTIUZ, ALESSIO
Physics-based modeling of high burnup structure porosity in UO2 fuel: implementation and validation in SCIANTIX
2024/2025 Frattini, Ulisse
Preliminary neutronics and thermo-micro-mechanical analyses of nuclear fuel from AP1000 reactor
2024/2025 Rizzetto, Lorenzo
Mostrati risultati da 1 a 17 di 17
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