Archivio Istituzionale della RicercaABRATE, NICOLO'
ABRATE, NICOLO'
Dipartimento Energia
046228
An OpenFOAM solver for multiphysics modeling of fusion reactor design: The nemoFoam code
2024 Caravello, M.; Aimetta, A.; Abrate, N.; Dulla, S.; Froio, A.
Development of a New Thermal-Hydraulic Module for FRENETIC, a Code for the Multiphysics Analysis of Liquid Metal–Cooled Reactors
2024 Lombardo, Antonino; Nallo, Giuseppe F.; Abrate, Nicolo; Liu, Yapeng; Dulla, Sandra
Spectrum features of the eigenvalue formulations in neutron transport
2024 Abrate, Nicolo; Dulla, Sandra; Ravetto, Piero; Saracco, Paolo
Spectrum features of the eigenvalue formulations in neutron transport (dataset)
2024 Abrate, Nicolo'
A generalised eigenvalue formulation for core-design applications
2023 Abrate, Nicolo; Dulla, Sandra; Ravetto, Piero; Saracco, Paolo
A non-intrusive reduced order model for the characterisation of the spatial power distribution in large thermal reactors
2023 Abrate, Nicolo'; Dulla, Sandra; Pedroni, Nicola
A non-intrusive reduced order model for the characterisation of the spatial power distribution in large thermal reactors (dataset)
2023 Abrate, Nicolo'
A Nonintrusive Nuclear Data Uncertainty Propagation Study for the ARC Fusion Reactor Design
2023 Aimetta, Alex; Abrate, Nicolo; Dulla, Sandra; Froio, Antonio
A novel approach combining bootstrapped non-intrusive reduced order models and unscented transform for the robust and efficient CFD analysis of accidental gas releases in congested plants
2023 Abrate, Nicolo'; Pedroni, Nicola; Moscatello, Alberto; Carpignano, Andrea; Carbone, Federica; Maffia, Manuela; Ledda, Gianmario
Alternative Weighting Functions for Group Collapsing of Nuclear Data in Lead Fast Reactors Time-dependent Analyses
2023 Abrate, Nicolo; Vita, Christian; Dulla, Sandra; Ravetto, Piero; Saracco, Paolo
Development of a new Thermal-Hydraulic Module for FRENETIC, a Code for the Multiphysics Analysis of Liquid Metal-Cooled Reactors
2023 Lombardo, A.; Nallo, G. F.; Abrate, N.; Dulla, S.
Modelling the PbLi flow including tritium transport and permeation with GETTHEM
2023 Bonifetto, R.; Abrate, N.; Froio, A.; Lisanti, F.; Papa, F.; Utili, M.; Venturini, A.
Non-intrusive Uncertainty Propagation in the ARC Fusion Reactor through the nemoFOAM Multi-physics Tool
2023 Aimetta, A.; Caravello, M.; Abrate, N.; Dulla, S.; Froio, A.
Nuclear Data Uncertainty Propagation for the Molten Salt Fast Reactor Design
2023 Abrate, Nicolo’; Aimetta, Alex; Dulla, Sandra; Pedroni, Nicola
Nuclear Data Uncertainty Propagation for the Molten Salt Fast Reactor Design (dataset)
2023 Abrate, Nicolo'; Aimetta, Alex
Code-to-code SIMMER/FRENETIC comparison for the neutronic simulation of lead-cooled fast reactors
2022 Massone, Mattia; Abrate, Nicolo; Nallo, GIUSEPPE FRANCESCO; Valerio, Domenico; Dulla, Sandra; Ravetto, Piero
Code-to-code SIMMER/FRENETIC comparison for the neutronic simulation of lead-cooled fast reactors (dataset)
2022 Nallo, GIUSEPPE FRANCESCO; Abrate, Nicolo; Dulla, Sandra; Ravetto, Piero; Massone, Mattia; Valerio, Domenico
Formulation of the Density Eigenvalue Problemin Neutron Transport for Relevant Engineering Applications
2022 Abrate, Nicolo'; Dulla, Sandra; Saracco, Paolo; Ravetto, Piero
Genetic algorithm-based optimisation of the few-group structure for lead fast reactor analysis
2022 Massone, MATTIA VINCENZO EDOARDO; Abrate, Nicolo'; Nallo, GIUSEPPE FRANCESCO; Valerio, Domenico; Dulla, Sandra; Ravetto, Piero
Methods for safety and stability analysis of nuclear systems
2022 Abrate, Nicolo'
| Citazione | Data di pubblicazione | Autori | File |
|---|---|---|---|
| An OpenFOAM solver for multiphysics modeling of fusion reactor design: The nemoFoam code / Caravello, M.; Aimetta, A.; Abrate, N.; Dulla, S.; Froio, A.. - In: NUCLEAR MATERIALS AND ENERGY. - ISSN 2352-1791. - STAMPA. - 40:(2024). [10.1016/j.nme.2024.101693] | 1-gen-2024 | Caravello, M.Aimetta, A.Abrate, N.Dulla, S.Froio, A. | 2024_Caravello_nemoFoam.pdf |
| Development of a New Thermal-Hydraulic Module for FRENETIC, a Code for the Multiphysics Analysis of Liquid Metal–Cooled Reactors / Lombardo, Antonino; Nallo, Giuseppe F.; Abrate, Nicolo; Liu, Yapeng; Dulla, Sandra. - In: NUCLEAR TECHNOLOGY. - ISSN 0029-5450. - ELETTRONICO. - Selected papers from the NURETH-20 special issue:(2024), pp. 1-18. [10.1080/00295450.2024.2397189] | 1-gen-2024 | Nallo, Giuseppe F.Abrate, NicoloDulla, Sandra + | - |
| Spectrum features of the eigenvalue formulations in neutron transport / Abrate, Nicolo; Dulla, Sandra; Ravetto, Piero; Saracco, Paolo. - In: ANNALS OF NUCLEAR ENERGY. - ISSN 0306-4549. - ELETTRONICO. - 201:(2024). [10.1016/j.anucene.2024.110421] | 1-gen-2024 | Abrate, NicoloDulla, SandraRavetto, Piero + | 1-s2.0-S0306454924000835-main.pdf |
| Spectrum features of the eigenvalue formulations in neutron transport (dataset) / Abrate, Nicolo'. - (2024). [10.5281/zenodo.10608508] | 1-gen-2024 | Nicolo' Abrate | - |
| A generalised eigenvalue formulation for core-design applications / Abrate, Nicolo; Dulla, Sandra; Ravetto, Piero; Saracco, Paolo. - In: NUCLEAR SCIENCE AND ENGINEERING. - ISSN 0029-5639. - (2023). [10.1080/00295639.2022.2134685] | 1-gen-2023 | Nicolo AbrateSandra DullaPiero Ravetto + | A_generalised_eigenvalue_formulation_for_core_design_applications.pdf; A Generalized Eigenvalue Formulation for Core Design Applications(1).pdf |
| A non-intrusive reduced order model for the characterisation of the spatial power distribution in large thermal reactors / Abrate, Nicolo'; Dulla, Sandra; Pedroni, Nicola. - In: ANNALS OF NUCLEAR ENERGY. - ISSN 0306-4549. - ELETTRONICO. - 184:(2023), p. 109674. [10.1016/j.anucene.2022.109674] | 1-gen-2023 | Nicolo AbrateSandra DullaNicola Pedroni | 1-s2.0-S0306454922007046-main(1).pdf; A_non_intrusive_reduced_order_model_for_the_spatial_stability_analysis_of_large_thermal_reactors(1)_compressed.pdf |
| A non-intrusive reduced order model for the characterisation of the spatial power distribution in large thermal reactors (dataset) / Abrate, Nicolo'. - (2023). [10.5281/zenodo.7472108] | 1-gen-2023 | Nicolo Abrate | - |
| A Nonintrusive Nuclear Data Uncertainty Propagation Study for the ARC Fusion Reactor Design / Aimetta, Alex; Abrate, Nicolo; Dulla, Sandra; Froio, Antonio. - In: NUCLEAR SCIENCE AND ENGINEERING. - ISSN 0029-5639. - ELETTRONICO. - 197:8(2023), pp. 2192-2216. [10.1080/00295639.2022.2153638] | 1-gen-2023 | Alex AimettaNicolo AbrateSandra DullaAntonio Froio | A Nonintrusive Nuclear Data Uncertainty Propagation Study for the ARC Fusion Reactor Design.pdf; ARC.pdf |
| A novel approach combining bootstrapped non-intrusive reduced order models and unscented transform for the robust and efficient CFD analysis of accidental gas releases in congested plants / Abrate, Nicolo'; Pedroni, Nicola; Moscatello, Alberto; Carpignano, Andrea; Carbone, Federica; Maffia, Manuela; Ledda, Gianmario. - In: JOURNAL OF LOSS PREVENTION IN THE PROCESS INDUSTRIES. - ISSN 1873-3352. - 83:(2023), pp. 1-17. [10.1016/j.jlp.2023.105015] | 1-gen-2023 | Abrate NicoloNicola PedroniAlberto MoscatelloAndrea CarpignanoGianmario Ledda + | ROM_SB_JLOSS_review_1.pdf; 1-s2.0-S0950423023000451-main.pdf |
| Alternative Weighting Functions for Group Collapsing of Nuclear Data in Lead Fast Reactors Time-dependent Analyses / Abrate, Nicolo; Vita, Christian; Dulla, Sandra; Ravetto, Piero; Saracco, Paolo. - ELETTRONICO. - (2023). (Intervento presentato al convegno M&C 2023 - The International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering tenutosi a Niagara Falls (Canada) nel August 13 – 17, 2023). | 1-gen-2023 | Nicolo AbrateChristian VitaSandra DullaPiero Ravetto + | - |
| Development of a new Thermal-Hydraulic Module for FRENETIC, a Code for the Multiphysics Analysis of Liquid Metal-Cooled Reactors / Lombardo, A.; Nallo, G. F.; Abrate, N.; Dulla, S.. - ELETTRONICO. - (2023), pp. 3663-3676. (Intervento presentato al convegno 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023 tenutosi a Washington nel 20 August 2023 through 25 August 2023) [10.13182/nureth20-40847]. | 1-gen-2023 | Nallo, G. F.Abrate, N.Dulla, S. + | - |
| Modelling the PbLi flow including tritium transport and permeation with GETTHEM / Bonifetto, R.; Abrate, N.; Froio, A.; Lisanti, F.; Papa, F.; Utili, M.; Venturini, A.. - In: NUCLEAR MATERIALS AND ENERGY. - ISSN 2352-1791. - ELETTRONICO. - 37:(2023). [10.1016/j.nme.2023.101500] | 1-gen-2023 | Bonifetto R.Abrate N.Froio A.Lisanti F. + | 1-s2.0-S2352179123001394-main.pdf |
| Non-intrusive Uncertainty Propagation in the ARC Fusion Reactor through the nemoFOAM Multi-physics Tool / Aimetta, A.; Caravello, M.; Abrate, N.; Dulla, S.; Froio, A.. - ELETTRONICO. - (2023). (Intervento presentato al convegno M&C 2023 - The International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering tenutosi a Niagara Falls (Canada) nel August 13 – 17, 2023). | 1-gen-2023 | A. AimettaM. CaravelloN. AbrateS. DullaA. Froio | FinalPaper_381_0806062559.pdf |
| Nuclear Data Uncertainty Propagation for the Molten Salt Fast Reactor Design / Abrate, Nicolo’; Aimetta, Alex; Dulla, Sandra; Pedroni, Nicola. - In: NUCLEAR SCIENCE AND ENGINEERING. - ISSN 0029-5639. - ELETTRONICO. - (2023), pp. 1-23. [10.1080/00295639.2023.2190861] | 1-gen-2023 | Nicolo’ AbrateAlex AimettaSandra DullaNicola Pedroni | UQ_MSFR.pdf; Nuclear Data Uncertainty Propagation for the Molten Salt Fast Reactor Design(1).pdf |
| Nuclear Data Uncertainty Propagation for the Molten Salt Fast Reactor Design (dataset) / Abrate, Nicolo'; Aimetta, Alex. - (2023). [10.5281/zenodo.7937502] | 1-gen-2023 | Nicolo AbrateAlex Aimetta | - |
| Code-to-code SIMMER/FRENETIC comparison for the neutronic simulation of lead-cooled fast reactors / Massone, Mattia; Abrate, Nicolo; Nallo, GIUSEPPE FRANCESCO; Valerio, Domenico; Dulla, Sandra; Ravetto, Piero. - In: ANNALS OF NUCLEAR ENERGY. - ISSN 0306-4549. - ELETTRONICO. - 174:(2022), p. 109124. [10.1016/j.anucene.2022.109124] | 1-gen-2022 | Nicolo AbrateGiuseppe Francesco NalloDomenico ValerioSandra DullaPiero Ravetto + | Massone et al. - 2021 - Code-to-code SIMMER FRENETIC comparison for the neutronic simulation of lead-cooled fast reactors.pdf; accepted_ms.pdf |
| Code-to-code SIMMER/FRENETIC comparison for the neutronic simulation of lead-cooled fast reactors (dataset) / Nallo, GIUSEPPE FRANCESCO; Abrate, Nicolo; Dulla, Sandra; Ravetto, Piero; Massone, Mattia; Valerio, Domenico. - (2022). [10.5281/zenodo.6483981.svg] | 1-gen-2022 | Nallo Giuseppe FrancescoAbrate NicoloDulla SandraRavetto PieroValerio Domenico + | - |
| Formulation of the Density Eigenvalue Problemin Neutron Transport for Relevant Engineering Applications / Abrate, Nicolo'; Dulla, Sandra; Saracco, Paolo; Ravetto, Piero. - ELETTRONICO. - (2022), pp. 933-942. (Intervento presentato al convegno PHYSOR 2022 International Conference tenutosi a Pittsburgh, PA, U.S.A. nel May 15-20, 2022). | 1-gen-2022 | Nicolo AbrateSandra DullaPaolo SaraccoPiero Ravetto | proc_v_n_pp933-942.pdf; Formulation of the Density Eigenvalue Problem in Neutron Transport for Relevant Engineering Applications.pdf |
| Genetic algorithm-based optimisation of the few-group structure for lead fast reactor analysis / Massone, MATTIA VINCENZO EDOARDO; Abrate, Nicolo'; Nallo, GIUSEPPE FRANCESCO; Valerio, Domenico; Dulla, Sandra; Ravetto, Piero. - ELETTRONICO. - (2022), pp. 1388-1397. (Intervento presentato al convegno PHYSOR 2022 International Conference tenutosi a Pittsburgh, PA, U.S.A. nel May 15-20, 2022). | 1-gen-2022 | Mattia MassoneNicolo AbrateGiuseppe Francesco NalloDomenico ValerioSandra DullaPiero Ravetto | proc_v_n_pp1388-1397.pdf; main.pdf; BS EN ISO 7751-2016--[2022-10-14--01-45-39 PM].pdf |
| Methods for safety and stability analysis of nuclear systems / Abrate, Nicolo'. - (2022 Sep 16), pp. 1-325. | 16-set-2022 | ABRATE, NICOLO' | Abrate_PhD_thesis_pre_review.pdf; Abrate_PhD_summary.pdf |