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
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
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.
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.
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
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
“On the Foundation of Transport-Driven Diffusion for Neutron Transport Problems”
2022 Picca, Paolo; Furfaro, Roberto; Dulla, Sandra; Ravetto, Piero
Erratum: “Radiative heat load distribution on the EU-DEMO first wall due to mitigated disruptions” (Nuclear Materials and Energy (2020) 25, (S2352179120300971), (10.1016/j.nme.2020.100824))
2021 Moscheni, M.; Carr, M.; Dulla, S.; Maviglia, F.; Meakins, A.; Nallo, G. F.; Subba, F.; Zanino, R.
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.
Parametric study of the radiative load distribution on the EU-DEMO first wall due to SPI-mitigated disruptions
2021 Moscheni, M.; Carr, M.; Dulla, S.; Maviglia, F.; Meakins, A.; Nallo, G. F.; Subba, F.; Zanino, R.
Preliminary uncertainty and sensitivity analysis of the Molten Salt Fast Reactor steady-state using a Polynomial Chaos Expansion method
2021 Santanoceto, Mario; Tiberga, Marco; Perkó, Zoltán; Dulla, Sandra; Lathouwers, Danny
A MOC-based neutron kinetics model for noise analysis
2020 Gammicchia, A.; Santandrea, S.; Zmijarevic, I.; Sanchez, R.; Stankovski, Z.; Dulla, S.; Mosca, P.
A re-visitation of space asymptotic theory in neutron transport
2020 Dulla, S.; Ravetto, P.
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 |
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 |
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. + | - |
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 |
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 |
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 |
“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.pdf; On the Foundation of Transport Driven Diffusion for Neutron Transport Problems.pdf |
Erratum: “Radiative heat load distribution on the EU-DEMO first wall due to mitigated disruptions” (Nuclear Materials and Energy (2020) 25, (S2352179120300971), (10.1016/j.nme.2020.100824)) / Moscheni, M.; Carr, M.; Dulla, S.; Maviglia, F.; Meakins, A.; Nallo, G. F.; Subba, F.; Zanino, R.. - In: NUCLEAR MATERIALS AND ENERGY. - ISSN 2352-1791. - ELETTRONICO. - 27:(2021), p. 100978. [10.1016/j.nme.2021.100978] | 1-gen-2021 | Moscheni M.Dulla S.Nallo G. F.Subba F.Zanino R. + | 1-s2.0-S2352179121000612-main.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 |
Parametric study of the radiative load distribution on the EU-DEMO first wall due to SPI-mitigated disruptions / Moscheni, M.; Carr, M.; Dulla, S.; Maviglia, F.; Meakins, A.; Nallo, G. F.; Subba, F.; Zanino, R.. - In: FUSION ENGINEERING AND DESIGN. - ISSN 0920-3796. - ELETTRONICO. - 172:(2021), p. 112917. [10.1016/j.fusengdes.2021.112917] | 1-gen-2021 | Moscheni M.Dulla S.Nallo G. F.Subba F.Zanino R. + | Moscheni_CHERAB_SOFT_v4.8_accepted.pdf; Moscheni_CHERAB_SOFT_print.pdf |
Preliminary uncertainty and sensitivity analysis of the Molten Salt Fast Reactor steady-state using a Polynomial Chaos Expansion method / Santanoceto, Mario; Tiberga, Marco; Perkó, Zoltán; Dulla, Sandra; Lathouwers, Danny. - In: ANNALS OF NUCLEAR ENERGY. - ISSN 0306-4549. - 159:(2021), p. 108311. [10.1016/j.anucene.2021.108311] | 1-gen-2021 | Dulla, Sandra + | 1-s2.0-S0306454921001870-main.pdf |
A MOC-based neutron kinetics model for noise analysis / Gammicchia, A.; Santandrea, S.; Zmijarevic, I.; Sanchez, R.; Stankovski, Z.; Dulla, S.; Mosca, P.. - In: ANNALS OF NUCLEAR ENERGY. - ISSN 0306-4549. - 137:(2020), p. 107070. [10.1016/j.anucene.2019.107070] | 1-gen-2020 | Gammicchia A.Dulla S. + | TJ 62 - ANE Noise CEA.pdf; ANUCENE-D-19-00728_MOC_AAM.pdf |
A re-visitation of space asymptotic theory in neutron transport / Dulla, S.; Ravetto, P.. - In: THE EUROPEAN PHYSICAL JOURNAL PLUS. - ISSN 2190-5444. - STAMPA. - 135:4(2020). [10.1140/epjp/s13360-020-00324-9] | 1-gen-2020 | Dulla S.Ravetto P. | TJ 65 - EPJ+ Asymptotic.pdf |