ABRATE, NICOLO'

ABRATE, NICOLO'  

Dipartimento Energia  

046228  

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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
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.pdfA 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).pdfA_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.pdfARC.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.pdf1-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 + -
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.pdfNuclear 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.pdfaccepted_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.pdfFormulation 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.pdfmain.pdfBS 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.pdfAbrate_PhD_summary.pdf
Neutronic Analysis of the Fusion Reactor ARC: Monte Carlo Simulations with the Serpent Code / Aimetta, Alex; Abrate, Nicolo'; Dulla, Sandra; Froio, Antonio. - In: FUSION SCIENCE AND TECHNOLOGY. - ISSN 1536-1055. - STAMPA. - 78:4(2022), pp. 275-290. [10.1080/15361055.2021.2003151] 1-gen-2022 Alex AimettaNicolò AbrateSandra DullaAntonio Froio Neutronic Analysis of the Fusion Reactor ARC Monte Carlo Simulations with the Serpent Code_inPress.pdfARC.pdf
Nuclear data uncertainty quantification in the ARC fusion reactor / Aimetta, Alex; Abrate, Nicolo'; Dulla, Sandra; Froio, Antonio. - ELETTRONICO. - (2022), pp. 2952-2962. (Intervento presentato al convegno International Conference on Physics of Reactors 2022 (PHYSOR 2022) tenutosi a Pittsburgh, PA, U.S.A. nel May 15-20, 2022) [10.13182/PHYSOR22-37861]. 1-gen-2022 Alex AimettaNicolo AbrateSandra DullaAntonio Froio proc_v_n_pp2952-2962.pdfNUCLEAR_DATA_UNCERTAINTY_QUANTIFICATION_IN_THE_ARC_FUSION_REACTOR.pdf