Nicolo' Abrate

• Annual ENEN PhD Prize conferred by European Nuclear Education Network Association, Francia (2022)
• Outstanding Student Paper Award - PHYSOR Conference conferred by American Nuclear Society, Italy (2022)
• PhD Talent Award - Associazione Italiana Nucleare (AIN) conferred by Associazione Italiana Nucleare, Italy (2024)

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

PhD

• Numerical methods for neutron transport. A.A. 2024/25, ENERGETICA. Teaching assistant
• Numerical methods for neutron transport. A.A. 2023/24, ENERGETICA. Teaching assistant
• Numerical methods for neutron transport. A.A. 2022/23, ENERGETICA. Teaching assistant

Master of Science

• Nuclear fission reactor physics and transport theory. A.A. 2025/26, 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. 2025/26, 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. 2025/26, INGEGNERIA ENERGETICA E NUCLEARE. Collaboratore del corso
• Biomedical and industrial applications of radiation. A.A. 2025/26, INGEGNERIA ENERGETICA E NUCLEARE. Collaboratore del corso
• Nuclear fission reactor physics and transport theory. A.A. 2024/25, 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. 2024/25, 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. 2024/25, INGEGNERIA ENERGETICA E NUCLEARE. Collaboratore del corso
• Biomedical and industrial applications of radiation. A.A. 2024/25, INGEGNERIA ENERGETICA E NUCLEARE. Collaboratore del corso
• Nuclear fission reactor physics and transport theory. A.A. 2023/24, 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. 2023/24, 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. 2023/24, INGEGNERIA ENERGETICA E NUCLEARE. Collaboratore del corso
• Biomedical and industrial applications of radiation. A.A. 2023/24, INGEGNERIA ENERGETICA E NUCLEARE. Collaboratore del corso
• Nuclear fission reactor physics and transport theory. A.A. 2022/23, 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. 2022/23, 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. 2022/23, 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. 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
• Nuclear fission reactor physics and transport theory. 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. 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. 2019/20, INGEGNERIA ENERGETICA E NUCLEARE. Collaboratore del corso

Bachelor of Science

• Elementi di ingegneria nucleare. A.A. 2025/26, INGEGNERIA ENERGETICA. Collaboratore del corso
• Elementi di ingegneria nucleare. A.A. 2024/25, INGEGNERIA ENERGETICA. Collaboratore del corso
• Elementi di ingegneria nucleare. A.A. 2023/24, INGEGNERIA ENERGETICA. Collaboratore del corso
• Elementi di ingegneria nucleare. A.A. 2022/23, INGEGNERIA ENERGETICA. Collaboratore del corso
• Elementi di ingegneria nucleare. A.A. 2021/22, INGEGNERIA ENERGETICA. Collaboratore del corso
• Elementi di ingegneria nucleare. A.A. 2020/21, INGEGNERIA ENERGETICA. Collaboratore del corso
• Sicurezza degli impianti energetici. A.A. 2020/21, 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

• Gruppo di Ricerca NEMO (DENERG)

Projects funded by competitive calls

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

• George Afful. Programme in Energetica (40^th cycle, 2025-in progress)
• Massimo Quarta. Programme in Energetica (40^th cycle, 2024-in progress)
• Christian Vita. Programme in Energetica (39^th cycle, 2023-in progress)

• Dulla, Sandra; Abrate, Nicolo; Ravetto, Piero; Saracco, Paolo; Carta, Mario; Fabrizio, ... (2025)
  Impact of energy collapsing on the effective neutron lifetime. In: ANNALS OF NUCLEAR ENERGY, vol. 222. ISSN 0306-4549
  Contributo su Rivista
• Abrate, Nicolo; Aimetta, Alex; Massone, Mattia; Dulla, Sandra; Ravetto, Piero (2025)
  A Genetic-Driven Optimization of the Energy Grid Structure for Nodal Full-Core Calculations in Lead-Cooled Fast Reactors. In: NUCLEAR SCIENCE AND ENGINEERING, pp. 1-26. ISSN 0029-5639
  Contributo su Rivista
• Lombardo, Antonino; Nallo, Giuseppe F.; Abrate, Nicolo; Liu, Yapeng; Dulla, Sandra (2024)
  Development of a New Thermal-Hydraulic Module for FRENETIC, a Code for the Multiphysics Analysis of Liquid Metal–Cooled Reactors. In: NUCLEAR TECHNOLOGY, vol. Selected papers from the NURETH-20 special issue, pp. 1-18. ISSN 0029-5450
  Contributo su Rivista
• Caravello, M.; Aimetta, A.; Abrate, N.; Dulla, S.; Froio, A. (2024)
  An OpenFOAM solver for multiphysics modeling of fusion reactor design: The nemoFoam code. In: NUCLEAR MATERIALS AND ENERGY, vol. 40. ISSN 2352-1791
  Contributo su Rivista
• Abrate, Nicolo; Dulla, Sandra; Ravetto, Piero; Saracco, Paolo (2024)
  Spectrum features of the eigenvalue formulations in neutron transport. In: ANNALS OF NUCLEAR ENERGY, vol. 201. ISSN 0306-4549
  Contributo su Rivista
• Aimetta, A.; Caravello, M.; Abrate, N.; Dulla, S.; Froio, A. (2023)
  Non-intrusive Uncertainty Propagation in the ARC Fusion Reactor through the nemoFOAM Multi-physics Tool. In: M&C 2023 - The International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Niagara Falls (Canada), August 13 – 17, 2023
  Contributo in Atti di Convegno (Proceeding)
• Bonifetto, R.; Abrate, N.; Froio, A.; Lisanti, F.; Papa, F.; Utili, M.; Venturini, A. (2023)
  Modelling the PbLi flow including tritium transport and permeation with GETTHEM. In: NUCLEAR MATERIALS AND ENERGY, vol. 37. ISSN 2352-1791
  Contributo su Rivista
• Aimetta, Alex; Abrate, Nicolo; Dulla, Sandra; Froio, Antonio (2023)
  A Nonintrusive Nuclear Data Uncertainty Propagation Study for the ARC Fusion Reactor Design. In: NUCLEAR SCIENCE AND ENGINEERING, vol. 197, pp. 2192-2216. ISSN 0029-5639
  Contributo su Rivista
• Abrate, Nicolo’; Aimetta, Alex; Dulla, Sandra; Pedroni, Nicola (2023)
  Nuclear Data Uncertainty Propagation for the Molten Salt Fast Reactor Design. In: NUCLEAR SCIENCE AND ENGINEERING, pp. 1-23. ISSN 0029-5639
  Contributo su Rivista
• Abrate, Nicolo'; Pedroni, Nicola; Moscatello, Alberto; Carpignano, Andrea; Carbone, ... (2023)
  A novel approach combining bootstrapped non-intrusive reduced order models and unscented transform for the robust and efficient CFD analysis of accidental gas releases in congested plants. In: JOURNAL OF LOSS PREVENTION IN THE PROCESS INDUSTRIES, vol. 83, pp. 1-17. ISSN 1873-3352
  Contributo su Rivista
• Abrate, Nicolo; Vita, Christian; Dulla, Sandra; Ravetto, Piero; Saracco, Paolo (2023)
  Alternative Weighting Functions for Group Collapsing of Nuclear Data in Lead Fast Reactors Time-dependent Analyses. In: M&C 2023 - The International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Niagara Falls (Canada), August 13 – 17, 2023
  Contributo in Atti di Convegno (Proceeding)
• Lombardo, A.; Nallo, G. F.; Abrate, N.; Dulla, S. (2023)
  Development of a new Thermal-Hydraulic Module for FRENETIC, a Code for the Multiphysics Analysis of Liquid Metal-Cooled Reactors. In: 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023, Washington, 20 August 2023 through 25 August 2023, pp. 3663-3676
  Contributo in Atti di Convegno (Proceeding)