Metodi per la analisi di sicurezza e stabilità di reattori nucleari

• The ENEN PhD Event & Prize is an action of the European Nuclear Education Network to support the Research and Science in the Nuclear fields promoting the works of the young scientists and researchers who start their careers finishing their PhD. It takes place on a yearly basis in the framework of the international congress in the field of nuclear science. The ENEN PhD Events are co-sponsored by the European Nuclear Education Network Association (ENEN), the European Commission Joint Research Centre (JRC), and the organizer of the international conference (FISA2022-EURADWASTE '22). All presentations are judged by the Jury members taking into account the quality of the submitted paper as well as the quality of the presentation itself. Moreover, the participation in the discussion and the clarity in answering the questions received are also taken into account in selecting the winners. The ENEN PhD prize will grant me 1000€ to cover the expenses to participate to an international conference and present the result of my research work. (2022)

• Collegio di Ingegneria Biomedica. Componente invitato
• Collegio di Ingegneria Elettrica ed Energetica. Componente invitato

Corso di laurea magistrale

• Nuclear fission reactor physics and transport theory. A.A. 2020/21, INGEGNERIA ENERGETICA E NUCLEARE. Collaboratore del corso
• Nuclear fission reactor physics and transport theory. A.A. 2021/22, INGEGNERIA ENERGETICA E NUCLEARE. Collaboratore del corso
• Monte Carlo methods, safety and risk analysis (modulo di Monte Carlo methods, safety and risk analysis A). A.A. 2019/20, INGEGNERIA ENERGETICA E NUCLEARE. Collaboratore del corso
• Monte Carlo methods, safety and risk analysis (modulo di Monte Carlo methods, safety and risk analysis A). A.A. 2020/21, INGEGNERIA ENERGETICA E NUCLEARE. Collaboratore del corso
• Monte Carlo methods, safety and risk analysis (modulo di Monte Carlo methods, safety and risk analysis B). A.A. 2020/21, INGEGNERIA ENERGETICA E NUCLEARE. Collaboratore del corso
• Monte Carlo methods, safety and risk analysis (modulo di Monte Carlo methods, safety and risk analysis A). A.A. 2021/22, INGEGNERIA ENERGETICA E NUCLEARE. Collaboratore del corso
• Monte Carlo methods, safety and risk analysis (modulo di Monte Carlo methods, safety and risk analysis B). A.A. 2021/22, INGEGNERIA ENERGETICA E NUCLEARE. Collaboratore del corso

Corso di laurea di 1° livello

• Uso ottimale e sicurezza degli impianti energetici. A.A. 2018/19, INGEGNERIA ENERGETICA. Collaboratore del corso
• Elementi di ingegneria nucleare. A.A. 2020/21, INGEGNERIA ENERGETICA. Collaboratore del corso
• Elementi di ingegneria nucleare. A.A. 2021/22, INGEGNERIA ENERGETICA. Collaboratore del corso
• Laboratorio computazionale di scambio termico e Fondamenti di macchine (modulo di Laboratorio computazionale di scambio termico). A.A. 2019/20, INGEGNERIA ENERGETICA. Collaboratore del corso
• Sicurezza degli impianti energetici. A.A. 2020/21, INGEGNERIA ENERGETICA. Collaboratore del corso

• Gruppo di Ricerca NEMO

Progetti finanziati da bandi competitivi

• ENDURANCE - EU kNowleDge hUb foR enAbling MolteN Salt ReaCtor safety development and dEployment , (2024-2028) - Componente gruppo di Ricerca
  Ricerca UE - HE - EURATOM

• George Afful. Corso in Energetica (ciclo 40, 2025-in corso)
• Massimo Quarta. Corso in Energetica (ciclo 40, 2024-in corso)
• Christian Vita. Corso in Energetica (ciclo 39, 2023-in corso)

• 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
  Contributo su Rivista
• Massone, Mattia; Abrate, Nicolo; Nallo, GIUSEPPE FRANCESCO; Valerio, Domenico; Dulla, ... (2022)
  Code-to-code SIMMER/FRENETIC comparison for the neutronic simulation of lead-cooled fast reactors. In: ANNALS OF NUCLEAR ENERGY, vol. 174. ISSN 0306-4549
  Contributo su Rivista
• Abrate, Nicolo' (2022)
  Methods for safety and stability analysis of nuclear systems. relatore: DULLA, SANDRA; PEDRONI, NICOLA; , 34. XXXIV Ciclo, P.: 325
  Doctoral Thesis
• Abrate, Nicolo'; Dulla, Sandra; Saracco, Paolo; Ravetto, Piero (2022)
  Formulation of the Density Eigenvalue Problemin Neutron Transport for Relevant Engineering Applications. In: PHYSOR 2022 International Conference, Pittsburgh, PA, U.S.A., May 15-20, 2022, pp. 933-942
  Contributo in Atti di Convegno (Proceeding)
• Aimetta, Alex; Abrate, Nicolo'; Dulla, Sandra; Froio, Antonio (2022)
  Nuclear data uncertainty quantification in the ARC fusion reactor. In: International Conference on Physics of Reactors 2022 (PHYSOR 2022), Pittsburgh, PA, U.S.A., May 15-20, 2022, pp. 2952-2962
  Contributo in Atti di Convegno (Proceeding)
• Abrate, Nicolo'; Dulla, Sandra; Pedroni, Nicola; Ravetto, Piero (2021)
  A non-intrusive reduced order model for neutronic transient analyses of the ALFRED reactor. In: Mathematics & Computation (M&C) 2021, Virtual Meeting, pp. 489-498
  Contributo in Atti di Convegno (Proceeding)
• Abrate, Nicolo'; Ganapol, Barry D.; Dulla, Sandra; Saracco, Paolo; Ravetto, Piero; Zoia, ... (2021)
  Convergence acceleration aspects in the solution of the PN neutron transport eigenvalue problem. In: Mathematics and Computation (M&C) 2021, Virtual Meeting, October 3-7 2021, pp. 1103-1112
  Contributo in Atti di Convegno (Proceeding)
• 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
  Contributo su Rivista
• 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
  Contributo su Rivista
• 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: 9789811485930
  Contributo in Atti di Convegno (Proceeding)
• Valerio, Domenico; Abrate, Nicolo'; Dulla, Sandra; Nallo, GIUSEPPE FRANCESCO; Ravetto, ... (2020)
  Coupled modelling of the EBR-II SHRT-45R including photon heat deposition. In: International Conference PHYSOR 2020. ISBN: 978-1-5272-6447-2
  Contributo in Atti di Convegno (Proceeding)
• Saracco, Paolo; Abrate, Nicolo; Burrone, Miriam; Dulla, Sandra; Ravetto, Piero (2020)
  STUDY OF THE EIGENVALUE SPECTRA OF THE NEUTRON TRANSPORT PROBLEM IN PN APPROXIMATION. In: International Conference PHYSOR 2020, Cambridge. ISBN: 978-1-5272-6447-2
  Contributo in Atti di Convegno (Proceeding)
• Nallo, G. F.; Abrate, N.; Dulla, S.; Ravetto, P.; Valerio, D. (2020)
  Neutronic benchmark of the FRENETIC code for the multiphysics analysis of lead fast reactors. In: THE EUROPEAN PHYSICAL JOURNAL PLUS, vol. 135. ISSN 2190-5444
  Contributo su Rivista