Sfoglia per Autore  

Opzioni
Mostrati risultati da 1 a 50 di 245
Titolo Data di pubblicazione Autori File
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 +
Final report on rod cladding failure during SGTR 1-gen-2023 G. ZulloD. PizzocriL. Luzzi +
Synthesis of the presentation of INSPYRE results to the User Group 1-gen-2023 L. LuzziA. MagniD. Pizzocri +
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 +
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 +
Experimental investigation and thermodynamic modelling of the ThF4-PuF3 phase diagram 1-gen-2023 L. Luzzi +
The SCIANTIX code for fission gas behaviour: Status, upgrades, separate-effect validation, and future developments 1-gen-2023 G. ZulloD. PizzocriL. Luzzi
Towards simulations of fuel rod behaviour during severe accidents by coupling TRANSURANUS with SCIANTIX and MFPR-F 1-gen-2023 G. ZulloD. PizzocriL. Luzzi +
Third Yearly Activity Report 1-gen-2023 D. PizzocriL. Luzzi +
Best practices and QA protocols for code development 1-gen-2023 D. PizzocriL. Luzzi +
Towards multi-physics description of fuel behaviour for accidental conditions 1-gen-2023 M. Di GennaroL. LuzziA. MagniD. Pizzocri +
Description of new meso-scale models and their implementation in fuel performance codes 1-gen-2023 A. MagniM. Di GennaroD. PizzocriG. ZulloL. Luzzi +
Fuel pin behaviour under irradiation with high Pu content: Benchmark exercise 1-gen-2023 D. Jaramillo SierraA. MagniL. LuzziD. Pizzocri +
Assessment of INSPYRE-extended fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment 1-gen-2023 L. LuzziT. BaraniA. MagniD. Pizzocri +
A modelling methodology for the description of helium behaviour accounting for the grain-size distribution 1-gen-2023 D. PizzocriA. CechetL. CogniniA. MagniL. Luzzi +
Fuel performance simulations of ESNII prototypes: Results on the MYRRHA case study 1-gen-2022 A. MagniL. LuzziD. Pizzocri +
Synthesis of INSPYRE results 1-gen-2022 L. LuzziA. MagniD. Pizzocri +
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 +
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 +
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 +
Simulation of the Melting Behavior of the UO2-Zircaloy Fuel Cladding System by Laser Heating 1-gen-2022 L. 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 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
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 +
Improved models of melting temperature and thermal conductivity for mixed oxide fuels doped with low minor actinide contents 1-gen-2022 A. 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 +
Physics-based modelling and validation of inter-granular helium behaviour in SCIANTIX 1-gen-2022 R. GiorgiA. CechetL. CogniniA. MagniD. PizzocriG. ZulloL. Luzzi +
Results of the applicative benchmark between TRANSURANUS and GERMINAL on the ASTRID case study 1-gen-2021 A. MagniL. LuzziD. Pizzocri +
Results of the benchmark between pre- and post-INSPYRE code versions on selected experimental cases 1-gen-2021 L. LuzziT. BaraniL. CogniniA. MagniD. Pizzocri +
The TRANSURANUS fuel performance code 1-gen-2021 A. MagniL. 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 +
Assessment of three European fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment 1-gen-2021 L. LuzziT. BaraniL. CogniniA. MagniD. 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 +
SiPM-matrix readout of two-phase argon detectors using electroluminescence in the visible and near infrared range 1-gen-2021 P. AntonioliR. ArditoG. De GuidoA. GhisiM. GrassiL. LuzziM. MarianiS. MoioliL. A. PellegriniF. PerottiF. Villa +
Three-dimensional reconstruction from experimental two-dimensional images: Application to irradiated metallic fuel 1-gen-2021 D. PizzocriF. AntonelloT. BaraniL. 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 +
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. +
Modelling fission gas behaviour in fast reactor (U,Pu)O2 fuel with BISON 1-gen-2021 F. VerdolinD. PizzocriT. BaraniL. Luzzi +
Incorporation and verification of models and properties in fuel performance codes 1-gen-2020 L. LuzziT. BaraniA. MagniD. Pizzocri +
Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications 1-gen-2020 A. MagniT. BaraniD. PizzocriL. Luzzi +
SCIANTIX: A new open source multi-scale code for fission gas behaviour modelling designed for nuclear fuel performance codes 1-gen-2020 D. PizzocriT. BaraniL. Luzzi
Modeling high burnup structure in oxide fuels for application to fuel performance codes. part I: High burnup structure formation 1-gen-2020 T BaraniD. PizzocriL. Luzzi +
Design and construction of a new detector to measure ultra-low radioactive-isotope contamination of argon 1-gen-2020 P. AntonioliS. ArcelliR. ArditoG. De GuidoA. GhisiF. GranatoR. LussanaL. LuzziM. MarianiS. MoioliE. PaoloniL. A. PellegriniF. PerottiF. Villa +
Modeling intra-granular fission gas bubble evolution and coarsening in uranium dioxide during in-pile transients 1-gen-2020 T. BaraniA. MagniD. PizzocriL. Luzzi +
Report on the improved models of melting temperature and thermal conductivity for MOX fuels and JOG 1-gen-2020 A. MagniL. Luzzi +
Synthesis of the inert gas behaviour models developed in INSPYRE 1-gen-2020 D. PizzocriT. BaraniL. CogniniL. LuzziA. Magni +
Modelling of the Behaviour of Inert Gases In Oxide and Mixed Oxide Nuclear Fuel under Design Basis Accident Conditions 1-gen-2019 L. LuzziT. BaraniL. CogniniD. Pizzocri
Multiscale modeling of fission gas behavior in U3Si2 under LWR conditions 1-gen-2019 T. BaraniD. PizzocriL. Luzzi +
Mostrati risultati da 1 a 50 di 245
Legenda icone

  •  file ad accesso aperto
  •  file disponibili sulla rete interna
  •  file disponibili agli utenti autorizzati
  •  file disponibili solo agli amministratori
  •  file sotto embargo
  •  nessun file disponibile