Archivio Istituzionale della RicercaABRATE, NICOLO'
ABRATE, NICOLO'
Dipartimento Energia
046228
Early warning in Molten Salt Fast Reactors based on a data-driven method for the online incident detection and diagnosis
2026 Abrate, N.; Pedroni, N.; Caruso, N.; Dulla, S.; Lorenzi, S.
A Genetic-Driven Optimization of the Energy Grid Structure for Nodal Full-Core Calculations in Lead-Cooled Fast Reactors
2025 Abrate, Nicolo; Aimetta, Alex; Massone, Mattia; Dulla, Sandra; Ravetto, Piero
High-precision eigenvalues of the neutron transport equation by the Carlvik method
2025 Saracco, Paolo; Abrate, Nicolo; Dulla, Sandra; Ravetto, Piero
Impact of energy collapsing on the effective neutron lifetime
2025 Dulla, Sandra; Abrate, Nicolo; Ravetto, Piero; Saracco, Paolo; Carta, Mario; Fabrizio, Valentina; Peluso, Vincenzo
Monte Carlo and Deterministic Implementations of the Zeta-Eigenvalue Equation for Efficient Criticality Searches
2025 Raffuzzi, Valeria; Abrate, Nicolo; Dulla, Sandra
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
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 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
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.
Nuclear Data Uncertainty Propagation for the Molten Salt Fast Reactor Design
2023 Abrate, Nicolo’; Aimetta, Alex; Dulla, Sandra; Pedroni, Nicola
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
Neutronic Analysis of the Fusion Reactor ARC: Monte Carlo Simulations with the Serpent Code
2022 Aimetta, Alex; Abrate, Nicolo'; Dulla, Sandra; Froio, Antonio
Generalized perturbation techniques for uncertainty quantification in lead-cooled fast reactors
2021 Abrate, N.; Dulla, S.; Ravetto, P.
On some features of the eigenvalue problem for the PN approximation of the neutron transport equation
2021 Abrate, N.; Dulla, S.; Ravetto, P.; Saracco, P.
Eigenvalue Formulations for the PN Approximation to the Neutron Transport Equation
2020 Abrate, N.; Burrone, M.; Dulla, S.; Ravetto, P.; Saracco, P.
Neutronic benchmark of the FRENETIC code for the multiphysics analysis of lead fast reactors
2020 Nallo, G. F.; Abrate, N.; Dulla, S.; Ravetto, P.; Valerio, D.
| Citazione | Data di pubblicazione | Autori | File |
|---|---|---|---|
| Early warning in Molten Salt Fast Reactors based on a data-driven method for the online incident detection and diagnosis / Abrate, N.; Pedroni, N.; Caruso, N.; Dulla, S.; Lorenzi, S.. - In: NUCLEAR ENGINEERING AND DESIGN. - ISSN 0029-5493. - ELETTRONICO. - 446:(2026). [10.1016/j.nucengdes.2025.114581] | 1-gen-2026 | Abrate, N.Pedroni, N.Dulla, S.Lorenzi, S. + | - |
| A Genetic-Driven Optimization of the Energy Grid Structure for Nodal Full-Core Calculations in Lead-Cooled Fast Reactors / Abrate, Nicolo; Aimetta, Alex; Massone, Mattia; Dulla, Sandra; Ravetto, Piero. - In: NUCLEAR SCIENCE AND ENGINEERING. - ISSN 0029-5639. - ELETTRONICO. - (2025), pp. 1-26. [10.1080/00295639.2024.2446130] | 1-gen-2025 | Abrate, NicoloAimetta, AlexDulla, SandraRavetto, Piero + | A_genetic_driven_optimisation_of_the_energy_grid_structure_for_nodal_full_core_calculations_in_LFR.pdf; Abrate+et+al.+-+2025+-+A+Genetic-Driven+Optimization+of+the+Energy+Grid+Structure+for+Nodal+Full-Core+Calculations+in+Lead - 1-14.pdf; Abrate+et+al.+-+2025+-+A+Genetic-Driven+Optimization+of+the+Energy+Grid+Structure+for+Nodal+Full-Core+Calculations+in+Lead - 15-27.pdf |
| High-precision eigenvalues of the neutron transport equation by the Carlvik method / Saracco, Paolo; Abrate, Nicolo; Dulla, Sandra; Ravetto, Piero. - In: ANNALS OF NUCLEAR ENERGY. - ISSN 0306-4549. - ELETTRONICO. - 224:(2025), pp. 1-7. [10.1016/j.anucene.2025.111672] | 1-gen-2025 | Abrate, NicoloDulla, SandraRavetto, Piero + | Saracco et al. - 2025 - High-precision eigenvalues of the neutron transport equation by the Carlvik method.pdf |
| Impact of energy collapsing on the effective neutron lifetime / Dulla, Sandra; Abrate, Nicolo; Ravetto, Piero; Saracco, Paolo; Carta, Mario; Fabrizio, Valentina; Peluso, Vincenzo. - In: ANNALS OF NUCLEAR ENERGY. - ISSN 0306-4549. - 222:(2025). [10.1016/j.anucene.2025.111550] | 1-gen-2025 | Dulla, SandraAbrate, NicoloRavetto, Piero + | Dulla et al. - 2025 - Impact of Energy Collapsing on the Effective Neutron Lifetime.pdf |
| Monte Carlo and Deterministic Implementations of the Zeta-Eigenvalue Equation for Efficient Criticality Searches / Raffuzzi, Valeria; Abrate, Nicolo; Dulla, Sandra. - In: NUCLEAR SCIENCE AND ENGINEERING. - ISSN 0029-5639. - ELETTRONICO. - (2025), pp. 1-15. [10.1080/00295639.2025.2568341] | 1-gen-2025 | Abrate, NicoloDulla, Sandra + | Monte Carlo and Deterministic Implementations of the Zeta-Eigenvalue Equation for Efficient Criticality Searches.pdf |
| 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 + | NT_NURETHSpecialIssue_Nallo_FRENETIC_asSubmitted_manuscript.pdf; 1-s2.0-S0029549324005697-main.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 |
| 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 Generalized Eigenvalue Formulation for Core Design Applications(1).pdf; A_generalised_eigenvalue_formulation_for_core_design_applications.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 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 |
| 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 |
| 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 |
| 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 |
| 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.pdf; ARC.pdf |
| Generalized perturbation techniques for uncertainty quantification in lead-cooled fast reactors / Abrate, N.; Dulla, S.; Ravetto, P.. - In: ANNALS OF NUCLEAR ENERGY. - ISSN 0306-4549. - ELETTRONICO. - 164:(2021), p. 108623. [10.1016/j.anucene.2021.108623] | 1-gen-2021 | Abrate N.Dulla S.Ravetto P. | ANE_SpecialIssue_GPT.pdf; 1-s2.0-S0306454921004990-main.pdf |
| On some features of the eigenvalue problem for the PN approximation of the neutron transport equation / Abrate, N.; Dulla, S.; Ravetto, P.; Saracco, P.. - In: ANNALS OF NUCLEAR ENERGY. - ISSN 0306-4549. - ELETTRONICO. - 163:(2021), p. 108477. [10.1016/j.anucene.2021.108477] | 1-gen-2021 | Abrate N.Dulla S.Ravetto P. + | ANE_PNeigenvalue.pdf; 1-s2.0-S0306454921003534-main.pdf |
| Eigenvalue Formulations for the PN Approximation to the Neutron Transport Equation / Abrate, N.; Burrone, M.; Dulla, S.; Ravetto, P.; Saracco, P.. - In: JOURNAL OF COMPUTATIONAL AND THEORETICAL TRANSPORT. - ISSN 2332-4309. - ELETTRONICO. - (2020), pp. 1-23. [10.1080/23324309.2020.1856879] | 1-gen-2020 | N. AbrateS. DullaP. Ravetto + | Abrate et al. - 2020 - Eigenvalue Formulations for the P N Approximation to the Neutron Transport Equation Eigenvalue Formulations for t-annotated.pdf |
| Neutronic benchmark of the FRENETIC code for the multiphysics analysis of lead fast reactors / Nallo, G. F.; Abrate, N.; Dulla, S.; Ravetto, P.; Valerio, D.. - In: THE EUROPEAN PHYSICAL JOURNAL PLUS. - ISSN 2190-5444. - STAMPA. - 135:2(2020). [10.1140/epjp/s13360-020-00171-8] | 1-gen-2020 | Nallo G. F.Abrate N.Dulla S.Ravetto P.Valerio D. | FRENETIC-paper-final(1).pdf; Nallo2020_Article_NeutronicBenchmarkOfTheFRENETI.pdf |