Sfoglia per Correlatore ZULLO, GIOVANNI
Mostrati risultati da 1 a 10 di 10
A digital twin approach for helium diffusivity in UO2 nuclear fuel based on SCIANTIX
2023/2024 Wang, Shuo
An AI-enhanced model of athermal fission gas release in SCIANTIX
2022/2023 PAGANI, ARIANNA
Assessment of advanced tools for 3D modelling of pellet-cladding mechanical interaction in nuclear fuel rods
2023/2024 RODRÍGUEZ YNYESTO SÁNCHEZ, JUAN
Chromia-doped UO2 fuel: engineering modeling of chromium solubility and fission gas diffusivity
2022/2023 NICODEMO, GIOVANNI
Extension of fuel performance simulation tools for innovative materials: TRISO and metallic fuel
2024/2025 FARINA, LUCA
Fission gas release during design basis accidents : surrogate and physics-based models for conventional and meso-scale nuclear fuel codes
2022/2023 PETROSILLO, GIACOMO
Implementation and assessment of a coolant-channel model for the analysis of fuel rods under reactivity-initiated accident conditions
2025/2026 Ferraro, Davide
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
Towards physics-based description of fuel fragmentation: fission gas behaviour at grain boundaries
2023/2024 Cappellari, Elisa
Mostrati risultati da 1 a 10 di 10
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