NICOLO' ABRATE
/nicolo.abrate)
Dottorando
Assegnista di Ricerca
Docente a contratto e/o collaboratore didattico
+39 0110904408 / 4408 (DENERG)
Pubblicazioni più recenti
Aimetta, Alex; Abrate, Nicolo'; Dulla, Sandra; Froio, Antonio (2022)
Neutronic Analysis of the Fusion Reactor ARC: Monte Carlo Simulations with the Serpent Code. In: FUSION SCIENCE AND TECHNOLOGY, vol. 78, pp. 275-290. ISSN 1536-1055
Neutronic Analysis of the Fusion Reactor ARC: Monte Carlo Simulations with the Serpent Code. In: FUSION SCIENCE AND TECHNOLOGY, vol. 78, pp. 275-290. ISSN 1536-1055
Abrate, N.; Dulla, S.; Ravetto, P. (2021)
Generalized perturbation techniques for uncertainty quantification in lead-cooled fast reactors. In: ANNALS OF NUCLEAR ENERGY, vol. 164. ISSN 0306-4549
Generalized perturbation techniques for uncertainty quantification in lead-cooled fast reactors. In: ANNALS OF NUCLEAR ENERGY, vol. 164. ISSN 0306-4549
Abrate, N.; Dulla, S.; Ravetto, P.; Saracco, P. (2021)
On some features of the eigenvalue problem for the PN approximation of the neutron transport equation. In: ANNALS OF NUCLEAR ENERGY, vol. 163. ISSN 0306-4549
On some features of the eigenvalue problem for the PN approximation of the neutron transport equation. In: ANNALS OF NUCLEAR ENERGY, vol. 163. ISSN 0306-4549
Abrate, N.; Dulla, S.; Ravetto, P. (2020)
Uncertainty quantification in frenetic calculations of ALFRED lead-cooled fast reactor. In: 2020 International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020, Corpus Christi and St. Catharine's Colleges, Corpus Christi and St. Catharine's Colleges, gbr, 2020, pp. 2542-2549. ISSN 2100-014X
Uncertainty quantification in frenetic calculations of ALFRED lead-cooled fast reactor. In: 2020 International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020, Corpus Christi and St. Catharine's Colleges, Corpus Christi and St. Catharine's Colleges, gbr, 2020, pp. 2542-2549. ISSN 2100-014X
Abrate, N.; Dulla, S.; Pedroni, N. (2020)
A non-intrusive reduced order model for light water reactor core stability analysis. In: 30th European Safety and Reliability Conference, ESREL 2020 and 15th Probabilistic Safety Assessment and Management Conference, PSAM 2020, Venice (Italy), 2020, pp. 4946-4952. ISBN: 978-981148593-0
A non-intrusive reduced order model for light water reactor core stability analysis. In: 30th European Safety and Reliability Conference, ESREL 2020 and 15th Probabilistic Safety Assessment and Management Conference, PSAM 2020, Venice (Italy), 2020, pp. 4946-4952. ISBN: 978-981148593-0