DULLA, SANDRA

DULLA, SANDRA  

Dipartimento Energia  

011663  

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Citazione Data di pubblicazione Autori File
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
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.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 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. - (2023), pp. 1-25. [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
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 AbrateSandra DullaPiero Ravetto + -
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.pdfPaper_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.pdfNuclear 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.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
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
Studsvik R2 Materials Test Reactor Ad Hoc Depletion Strategy for the Derivation of the Fuel Isotopic Composition of the MPCMIV Benchmark / Giaccardi, L.; Di Pasquale, S.; Dulla, S.; Cherubini, M.; Petruzzi, A.. - ELETTRONICO. - (2022). (Intervento presentato al convegno PHYSOR 2022 tenutosi a Pittsburgh nel Maggio 2022) [10.13182/PHYSOR22-37529]. 1-gen-2022 Dulla S. + CP 98 - PHYSOR2022_NINE.pdf
“On the Foundation of Transport-Driven Diffusion for Neutron Transport Problems” / Picca, Paolo; Furfaro, Roberto; Dulla, Sandra; Ravetto, Piero. - In: JOURNAL OF COMPUTATIONAL AND THEORETICAL TRANSPORT. - ISSN 2332-4325. - 51:5(2022), pp. 305-328. [10.1080/23324309.2022.2110897] 1-gen-2022 Paolo PiccaSandra DullaPiero Ravetto + foundation_of_TDD - revision May 2022 - v1.pdfOn the Foundation of Transport Driven Diffusion for Neutron Transport Problems.pdf