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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 +
Thermal hydraulic analysis of liquid-fueled molten salt reactors 1-gen-2024 A. CammiV. Di MarcelloA. PiniL. 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 +
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 +
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 +
Advanced interpretation of the SPHERE irradiation experiment with neutronics and fuel performance codes 1-gen-2024 L. LuzziA. MagniD. PizzocriM. Di Gennaro +
The SCIANTIX code for fission gas behaviour: Status, upgrades, separate-effect validation, and future developments 1-gen-2023 G. ZulloD. PizzocriL. Luzzi
Description of new meso-scale models and their implementation in fuel performance codes 1-gen-2023 A. MagniM. Di GennaroD. PizzocriG. ZulloL. Luzzi +
Towards multi-physics description of fuel behaviour for accidental conditions 1-gen-2023 M. Di GennaroL. LuzziA. MagniD. Pizzocri +
Best practices and QA protocols for code development 1-gen-2023 D. PizzocriL. Luzzi +
Third Yearly Activity Report 1-gen-2023 D. PizzocriL. Luzzi +
Fuel pin behaviour under irradiation with high Pu content: Benchmark exercise 1-gen-2023 D. Jaramillo SierraA. MagniL. LuzziD. Pizzocri +
Final report on rod cladding failure during SGTR 1-gen-2023 G. ZulloD. PizzocriL. Luzzi +
Detailed Work Plan for technical work Packages 1-gen-2023 L. Luzzi +
Assessment of INSPYRE-extended fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment 1-gen-2023 L. LuzziT. BaraniA. MagniD. Pizzocri +
Synthesis of the presentation of INSPYRE results to the User Group 1-gen-2023 L. LuzziA. MagniD. Pizzocri +
Towards simulations of fuel rod behaviour during severe accidents by coupling TRANSURANUS with SCIANTIX and MFPR-F 1-gen-2023 G. ZulloD. PizzocriL. Luzzi +
Experimental and model-based assessment of diffusion kinetics of actinides and oxygen during fuel fabrication and of fission products over in-pile use 1-gen-2023 L. 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 surrogate model for the helium production rate in fast reactor MOX fuels 1-gen-2023 D. PizzocriL. LuzziA. MagniG. Zullo +
Experimental investigation and thermodynamic modelling of the ThF4-PuF3 phase diagram 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 +
Simulation of QUENCH-06 experiment by MELCOR v2.2 with Uncertainty Analysis 1-gen-2023 L. Luzzi +
Modeling high burnup structure in oxide fuels for application to fuel performance codes. Part II: Porosity evolution 1-gen-2022 T BaraniD. PizzocriG. PastoreL. Luzzi +
Simulation of the Melting Behavior of the UO2-Zircaloy Fuel Cladding System by Laser Heating 1-gen-2022 L. Luzzi +
Synthesis of INSPYRE results 1-gen-2022 L. LuzziA. MagniD. Pizzocri +
Fuel performance simulations of ESNII prototypes: Results on the MYRRHA case study 1-gen-2022 A. MagniL. LuzziD. Pizzocri +
Improved models of melting temperature and thermal conductivity for mixed oxide fuels doped with low minor actinide contents 1-gen-2022 A. MagniL. Luzzi +
Near Term and Promising Long Term Options for the Deployment of Thorium Based Nuclear Energy 1-gen-2022 L. LuzziM. E. Ricotti +
On the use of spectral algorithms for the prediction of short-lived volatile fission product release: Methodology for bounding numerical error 1-gen-2022 G. ZulloD. PizzocriL. Luzzi
Extension and application of the TRANSURANUS code to the normal operating conditions of the MYRRHA reactor 1-gen-2022 A. MagniT. BaraniD. PizzocriL. Luzzi +
On the intra-granular behaviour of a cocktail of inert gases in oxide nuclear fuel: Methodological recommendation for accelerated experimental investigation 1-gen-2022 D. PizzocriL. Luzzi +
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 +
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 +
Results of the benchmark between pre- and post-INSPYRE code versions on selected experimental cases 1-gen-2021 L. LuzziT. BaraniL. CogniniA. MagniD. Pizzocri +
Results of the applicative benchmark between TRANSURANUS and GERMINAL on the ASTRID case study 1-gen-2021 A. MagniL. LuzziD. Pizzocri +
A Physics-Based Description of Inter-Granular Helium Behaviour in SCIANTIX for Application in Fuel Performance Codes 1-gen-2021 R. GiorgiA. CechetL. CogniniA. MagniD. PizzocriL. Luzzi +
Towards a physics-based description of intra-granular helium behaviour in oxide fuel for application in fuel performance codes 1-gen-2021 L. CogniniA. CechetT. BaraniD. PizzocriL. Luzzi +
Mostrati risultati da 1 a 50 di 262
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