| Generalized perturbation techniques for uncertainty quantification in lead-cooled fast reactors N Abrate, S Dulla, P Ravetto Annals of Nuclear Energy 164, 108623, 2021 | 10 | 2021 |
| Neutronic benchmark of the FRENETIC code for the multiphysics analysis of lead fast reactors GF Nallo, N Abrate, S Dulla, P Ravetto, D Valerio The European Physical Journal Plus 135 (2), 1-18, 2020 | 10 | 2020 |
| Assessment of numerical methods for the evaluation of higher-order harmonics in diffusion theory N Abrate, G Bruna, S Dulla, P Ravetto Annals of Nuclear Energy 128, 455-470, 2019 | 9 | 2019 |
| Neutronic analysis of the fusion reactor ARC: Monte Carlo simulations with the Serpent code A Aimetta, N Abrate, S Dulla, A Froio Fusion Science and technology 78 (4), 275-290, 2022 | 7 | 2022 |
| Nuclear Data Uncertainty Quantification in Molten Salt Reactors with XGPT N Abrate, M Aufiero, S Dulla, L Fiorito International Conference on Mathematics and Computational Methods applied to …, 2019 | 7 | 2019 |
| A Nonintrusive Nuclear Data Uncertainty Propagation Study for the ARC Fusion Reactor Design A Aimetta, N Abrate, S Dulla, A Froio Nuclear Science and Engineering 197 (8), 2192-2216, 2023 | 5 | 2023 |
| A non-intrusive reduced order model for the characterisation of the spatial power distribution in large thermal reactors N Abrate, S Dulla, N Pedroni Annals of Nuclear Energy 184, 109674, 2023 | 5 | 2023 |
| Code-to-code SIMMER/FRENETIC comparison for the neutronic simulation of lead-cooled fast reactors M Massone, N Abrate, GF Nallo, D Valerio, S Dulla, P Ravetto Annals of Nuclear Energy 174, 109124, 2022 | 5 | 2022 |
| On some features of the eigenvalue problem for the PN approximation of the neutron transport equation N Abrate, S Dulla, P Ravetto, P Saracco Annals of Nuclear Energy 163, 108477, 2021 | 5 | 2021 |
| Eigenvalue Formulations for the PN Approximation to the Neutron Transport Equation N Abrate, M Burrone, S Dulla, P Ravetto, P Saracco Journal of Computational and Theoretical Transport 50 (5), 407-429, 2021 | 5 | 2021 |
| Nuclear data uncertainty propagation for the molten salt fast reactor design N Abrate, A Aimetta, S Dulla, N Pedroni Nuclear Science and Engineering 197 (12), 2977-2999, 2023 | 3 | 2023 |
| Modelling the PbLi flow including tritium transport and permeation with GETTHEM R Bonifetto, N Abrate, A Froio, F Lisanti, F Papa, M Utili, A Venturini Nuclear Materials and Energy 37, 101500, 2023 | 2 | 2023 |
| CONVERGENCE ACCELERATION ASPECTS IN THE SOLUTION OF PN NEUTRON TRANSPORT EIGENVALUE PROBLEM N Abrate, B Ganapol, S Dulla, P Saracco, P Ravetto, A Zoia M&C 2021, CONVERGENCE ACCELERATION ASPECTS IN THE SOLUTION OF PN NEUTRON …, 2021 | 2 | 2021 |
| Convergence limits in perturbation theory N Abrate, G Bruna, S Dulla, P Ravetto International Conference on Mathematics Computational Methods and Reactor …, 2019 | 2 | 2019 |
| Development of a New Thermal-Hydraulic Module for FRENETIC, a Code for the Multiphysics Analysis of Liquid Metal–Cooled Reactors A Lombardo, GF Nallo, N Abrate, Y Liu, S Dulla Nuclear Technology, 1-18, 2024 | 1 | 2024 |
| An OpenFOAM solver for multiphysics modeling of fusion reactor design: The nemoFoam code M Caravello, A Aimetta, N Abrate, S Dulla, A Froio Nuclear Materials and Energy, 101693, 2024 | 1 | 2024 |
| A Generalized Eigenvalue Formulation for Core-Design Applications N Abrate, S Dulla, P Ravetto, P Saracco Nuclear Science and Engineering 197 (8), 2047-2071, 2023 | 1 | 2023 |
| A non-intrusive reduced order model for neutronic transient analyses of the ALFRED reactor N Abrate, S Dulla, N Pedroni, P Ravetto Mathematics & Computation (M&C) 2021, 489-498, 2021 | 1 | 2021 |
| Coupled modelling of the EBR-II SHRT-45R including photon heat deposition D Valerio, N Abrate, S Dulla, GF Nallo, R Piero EPJ Web of Conferences 247, 07014, 2021 | 1 | 2021 |
| A Non-Intrusive Reduced Order Model for Light Water Reactor core stability analysis N Abrate, S Dulla, N Pedroni 30th European Safety and Reliability Conference, ESREL 2020 and 15th …, 2020 | 1 | 2020 |
