MAGNI, ALESSIO

MAGNI, ALESSIO  

DIPARTIMENTO DI ENERGIA  

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Risultati 1 - 17 di 17 (tempo di esecuzione: 0.014 secondi).
Titolo Data di pubblicazione Autori File
A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools 1-gen-2018 D. PizzocriG. PastoreT. BaraniA. MagniL. Luzzi +
A modelling methodology for the description of helium behaviour accounting for the grain-size distribution 1-gen-2023 D. PizzocriA. CechetL. CogniniA. MagniL. Luzzi +
A new burn-up module for application in fuel performance calculations targeting the helium production rate in (U,Pu)O2 for fast reactors 1-gen-2021 Cechet A.Barani T.Cognini L.Lorenzi S.Magni A.Pizzocri D.Luzzi L. +
A surrogate model for the helium production rate in fast reactor MOX fuels 1-gen-2023 D. PizzocriL. LuzziA. MagniG. Zullo +
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 +
Application of the SCIANTIX fission gas behaviour module to the integral pin performance in sodium fast reactor irradiation conditions 1-gen-2022 A. MagniD. PizzocriL. Luzzi +
Assessment of INSPYRE-extended fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment 1-gen-2023 L. LuzziT. BaraniA. MagniD. Pizzocri +
Assessment of three European fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment 1-gen-2021 L. LuzziT. BaraniL. CogniniA. MagniD. Pizzocri +
Extension and application of the TRANSURANUS code to the normal operating conditions of the MYRRHA reactor 1-gen-2022 A. MagniT. BaraniD. PizzocriL. Luzzi +
Modeling intra-granular fission gas bubble evolution and coarsening in uranium dioxide during in-pile transients 1-gen-2020 T. BaraniA. MagniD. PizzocriL. Luzzi +
Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications 1-gen-2020 A. MagniT. BaraniD. PizzocriL. Luzzi +
Modelling of thermal conductivity and melting behaviour of minor actinide-MOX fuels and assessment against experimental and molecular dynamics data 1-gen-2021 A. MagniL. LuzziD. Pizzocri +
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 +
Physics-based modelling and validation of inter-granular helium behaviour in SCIANTIX 1-gen-2022 R. GiorgiA. CechetL. CogniniA. MagniD. PizzocriG. ZulloL. Luzzi +
Towards grain-scale modelling of the release of radioactive fission gas from oxide fuel. Part I: SCIANTIX 1-gen-2022 G. ZulloD. PizzocriA. MagniL. Luzzi +
Towards grain-scale modelling of the release of radioactive fission gas from oxide fuel. Part II: Coupling SCIANTIX with TRANSURANUS 1-gen-2022 G. ZulloD. PizzocriA. MagniL. Luzzi +
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 +