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Titolo Data di pubblicazione Autori File
Status and Planned Activities for the SCIANTIX Code Application to High Burnup Fuels 1-gen-2024 D. PizzocriT. BaraniA. MagniG. ZulloL. Luzzi
Transient simulation of the in-pile performance of a MA-bearing fuel pin 1-gen-2024 D. PizzocriA. MagniM. Di GennaroL. Luzzi +
Simulation and optimization of performance during normal operating conditions of a minor actinide-bearing fuel pin 1-gen-2024 A. MagniM. Di GennaroD. PizzocriL. Luzzi +
Melting behaviour of mixed plutonium and iron oxides: An experimental study 1-gen-2024 L. Luzzi +
A methodology for accelerated design of irradiation experiments: Demonstration via an OpenFOAM-informed TRANSURANUS simulation 1-gen-2024 M. Di GennaroA. MagniL. LuzziD. Pizzocri +
Chromia-doped UO2 fuel: An engineering model for chromium solubility and fission gas diffusivity 1-gen-2024 G. NicodemoG. ZulloL. LuzziD. Pizzocri +
Integral-scale validation of the SCIANTIX code for Light Water Reactor fuel rods 1-gen-2024 G. ZulloD. PizzocriL. Luzzi +
On the definition of the escape rate coefficient 1-gen-2024 D. PizzocriG. ZulloL. Luzzi +
Thermal hydraulic analysis of liquid-fueled molten salt reactors 1-gen-2024 A. CammiV. Di MarcelloA. PiniL. Luzzi
Description of new correlations and databases for fuel performance codes to be applied to Am bearing fuels 1-gen-2024 A. MagniM. Di GennaroD. PizzocriL. Luzzi +
Current Status and Planned Research Activities for the TRANSURANUS Code Application to High Burnup Fuels 1-gen-2024 D. PizzocriL. Luzzi +
Grain-Scale Modeling of Active Fission Product Behavior During Power Ramps with the Fission Gas Model MARGARET-PAF 1-gen-2024 C. IntroiniL. Luzzi +
Data Assimilation for Fuel Performance Code Development: Application to Oxide Fuel Thermal Properties 1-gen-2024 G. NicodemoD. PizzocriL. Luzzi +
Advanced interpretation of the SPHERE irradiation experiment with neutronics and fuel performance codes 1-gen-2024 L. LuzziA. MagniD. PizzocriM. Di Gennaro +
Towards modelling defective fuel rods in TRANSURANUS: Benchmark and assessment of gaseous and volatile radioactive fission product release 1-gen-2024 G. ZulloD. PizzocriA. MagniL. Luzzi +
Performance analysis and helium behaviour of Am-bearing fuel pins for irradiation in the MYRRHA reactor 1-gen-2024 L. LuzziA. MagniM. Di GennaroD. PizzocriM. ZanettiG. Zullo +
The SCIANTIX code for fission gas behaviour: Status, upgrades, separate-effect validation, and future developments 1-gen-2023 G. ZulloD. PizzocriL. Luzzi
Simulation of QUENCH-06 experiment by MELCOR v2.2 with Uncertainty Analysis 1-gen-2023 L. Luzzi +
Analysis of the performance of driver MOX fuel in the MYRRHA reactor under Beam Power Jump transient irradiation conditions 1-gen-2023 A. MagniM. Di GennaroD. PizzocriG. ZulloL. Luzzi +
A surrogate model for the helium production rate in fast reactor MOX fuels 1-gen-2023 D. PizzocriL. LuzziA. MagniG. Zullo +
Mostrati risultati da 1 a 20 di 262
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