DULLA, SANDRA
DULLA, SANDRA
Dipartimento Energia
011663
An OpenFOAM solver for multiphysics modeling of fusion reactor design: The nemoFoam code
2024 Caravello, M.; Aimetta, A.; Abrate, N.; Dulla, S.; Froio, A.
Application of the Polynomial Chaos Expansion to the Uncertainty Propagation in Fault Transients in Nuclear Fusion Reactors: DTT TF Fast Current Discharge
2024 De Bastiani, Marco; Aimetta, Alex; Bonifetto, Roberto; Dulla, Sandra
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
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
Cutting-edge R&D activities of CIRTEN in support of the Technology Park annexed to the Italian National Repository of radioactive waste
2023 Galluccio, F.; Macerata, E.; Magugliani, G.; Mariani, M.; Mossini, E.; Negrin, M.; Ricotti, M.; Santi, A.; Acquaro, D.; Cancemi, S. A.; Chierici, A.; Ciolini, R.; D'Errico, F.; Lo Frano, R.; Caruso, G.; D'Onorio, M.; Frullini, M.; Giannetti, F.; Gramiccia, L.; Tassone, A.; Sumini, M.; Isolan, L.; Malinconico, M.; Teodori, F.; Testa, M.; Bleynat, S.; Bonifetto, R.; Corrado, M.; Crivelli, F.; Dulla, S.; Froio, A.; Mauro, S.; Savoldi, L.; Testoni, R.; Troise, M.; Zanino, R.
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.
GRE@T-PIONEeR: Teaching the nuclear data pipeline using innovative pedagogical methods
2023 Cabellos, Oscar; Demazière, Christophe; Dulla, Sandra; Garcia-Herranz, Nuria; Miró, Rafael; Macian, Rafael; Szieberth, Máté; Buchet, Emma; Maurice, Suzi; Strola, Samy
Hybrid Monte Carlo/deterministic activation calculation to support the decommissioning of PWRs: Validation against data from the thermal shield of the Enrico Fermi NPP
2023 Bleynat, S.; Dulla, S.; Pancotti, F.; Ricci, L.; Vicini, C.; Zanino, R.
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 quantification on PWR spent nuclear fuel as a function of burnup
2023 Grimaldi, F; Romojaro, P; Fiorito, L; Belfiore, E; Bruggeman, C; Dulla, S
A Revisitation of the ENEA TAPIRO Fast Source Reactor Neutronic Capabilities
2022 Carta, M.; Burgio, N.; Fabrizio, V.; Falconi, L.; Peluso, V.; Santagata, A.; Dulla, S.
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
Citazione | Data di pubblicazione | Autori | File |
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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 |
Application of the Polynomial Chaos Expansion to the Uncertainty Propagation in Fault Transients in Nuclear Fusion Reactors: DTT TF Fast Current Discharge / De Bastiani, Marco; Aimetta, Alex; Bonifetto, Roberto; Dulla, Sandra. - In: APPLIED SCIENCES. - ISSN 2076-3417. - 14:3(2024). [10.3390/app14031068] | 1-gen-2024 | De Bastiani, MarcoAimetta, AlexBonifetto, RobertoDulla, Sandra | applsci-14-01068-v2.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 |
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 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 |
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 + | - |
Cutting-edge R&D activities of CIRTEN in support of the Technology Park annexed to the Italian National Repository of radioactive waste / Galluccio, F.; Macerata, E.; Magugliani, G.; Mariani, M.; Mossini, E.; Negrin, M.; Ricotti, M.; Santi, A.; Acquaro, D.; Cancemi, S. A.; Chierici, A.; Ciolini, R.; D'Errico, F.; Lo Frano, R.; Caruso, G.; D'Onorio, M.; Frullini, M.; Giannetti, F.; Gramiccia, L.; Tassone, A.; Sumini, M.; Isolan, L.; Malinconico, M.; Teodori, F.; Testa, M.; Bleynat, S.; Bonifetto, R.; Corrado, M.; Crivelli, F.; Dulla, S.; Froio, A.; Mauro, S.; Savoldi, L.; Testoni, R.; Troise, M.; Zanino, R.. - In: IL NUOVO CIMENTO C. - ISSN 2037-4909. - STAMPA. - 46:2(2023). [10.1393/ncc/i2023-23054-5] | 1-gen-2023 | Bleynat S.Bonifetto R.Corrado M.Crivelli F.Dulla S.Froio A.Mauro S.Savoldi L.Testoni R.Troise M.Zanino R. + | 2023_Galluccio_CIRTENDNPT_NuovoCimentoC.pdf |
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. + | - |
GRE@T-PIONEeR: Teaching the nuclear data pipeline using innovative pedagogical methods / Cabellos, Oscar; Demazière, Christophe; Dulla, Sandra; Garcia-Herranz, Nuria; Miró, Rafael; Macian, Rafael; Szieberth, Máté; Buchet, Emma; Maurice, Suzi; Strola, Samy. - In: EPJ WEB OF CONFERENCES. - ISSN 2100-014X. - 284:(2023). (Intervento presentato al convegno 15th International Conference on Nuclear Data for Science and Technology (ND2022)) [10.1051/epjconf/202328419001]. | 1-gen-2023 | Dulla, SandraStrola, Samy + | CP 99 - Great Pioneer 2023 EPJconf.pdf |
Hybrid Monte Carlo/deterministic activation calculation to support the decommissioning of PWRs: Validation against data from the thermal shield of the Enrico Fermi NPP / Bleynat, S.; Dulla, S.; Pancotti, F.; Ricci, L.; Vicini, C.; Zanino, R.. - In: ANNALS OF NUCLEAR ENERGY (ONLINE). - ISSN 1873-2100. - ELETTRONICO. - 181:(2023), pp. 1-12. [10.1016/j.anucene.2022.109527] | 1-gen-2023 | S. BleynatS. DullaR. Zanino + | Final.pdf; Paper_compressed.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 quantification on PWR spent nuclear fuel as a function of burnup / Grimaldi, F; Romojaro, P; Fiorito, L; Belfiore, E; Bruggeman, C; Dulla, S. - In: FRONTIERS IN ENERGY RESEARCH. - ISSN 2296-598X. - ELETTRONICO. - 11:(2023). [10.3389/fenrg.2023.1146598] | 1-gen-2023 | Belfiore, EDulla, S + | TJ 82 - Frontiers Grimaldi.pdf |
A Revisitation of the ENEA TAPIRO Fast Source Reactor Neutronic Capabilities / Carta, M.; Burgio, N.; Fabrizio, V.; Falconi, L.; Peluso, V.; Santagata, A.; Dulla, S.. - ELETTRONICO. - (2022). (Intervento presentato al convegno PHYSOR 2022 tenutosi a Pittsburgh nel Maggio 2022). | 1-gen-2022 | S. Dulla + | 37618_Physor_Dulla.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 |
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 |