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)

• Raffuzzi, Valeria; Abrate, Nicolo; Dulla, Sandra (2025)
  Monte Carlo and Deterministic Implementations of the Zeta-Eigenvalue Equation for Efficient Criticality Searches. In: NUCLEAR SCIENCE AND ENGINEERING, pp. 1-15. ISSN 0029-5639
  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
• Saracco, Paolo; Abrate, Nicolo; Dulla, Sandra; Ravetto, Piero (2025)
  High-precision eigenvalues of the neutron transport equation by the Carlvik method. In: ANNALS OF NUCLEAR ENERGY, vol. 224, pp. 1-7. ISSN 0306-4549
  Contributo su Rivista
• Caravello, M.; Abrate, N.; Aimetta, A.; Dulla, S.; Froio, A.; Zanino, R.; Mancini, N.; ... (2025)
  Development and validation of magneto-hydrodynamics turbulence models for the thermal-hydraulic design of fusion reactor liquid blankets. In: Fusion Energy Conference 2025, Chengdu (CN), 13-18/10/2025
  Contributo in Atti di Convegno (Proceeding)
• 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
• Vita, Christian; Abrate, Nicolo; Dulla, Sandra; Franceschini, Fausto (2025)
  Cross Sections Generation and SPH Correction Methods for Deterministic Code Simulation of the Westinghouse LFR Design. In: International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering M&C 2025, Denver (USA), 27-30 Aprile 2025, pp. 48-57
  Contributo in Atti di Convegno (Proceeding)
• Delvaux, Emilie; Grimaldi, Federico; Abrate, Nicolo; Aimetta, Alex; Massone, Mattia; ... (2025)
  Designing energy discretisations for sensitivity studies in lead-cooled fast reactors using a genetic algorithm. In: International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering M&C 2025, Denver (USA), 27-30 Aprile 2025, pp. 896-905
  Contributo in Atti di Convegno (Proceeding)
• Raffuzzi, Valeria; Abrate, Nicolo; Dulla, Sandra (2025)
  A Monte Carlo Implementation of the ζ-Eigenvalue Equation. In: International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering M&C 2025, Denver (USA), 27-30 Aprile 2025, pp. 1198-1207
  Contributo in Atti di Convegno (Proceeding)
• Abrate, Nicolo; Bousquet, Jeremy; Dulla, Sandra; Lo Muzio, Silvia; Seubert, Armin; Vita, ... (2025)
  The Neutronics Codes FENNECS and FRENETIC: Code-to-code Benchmarking on Lead and Sodium-cooled Fast Reactors. In: International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering M&C 2025, Denver (USA), 27-30 Aprile 2025, pp. 2123-2132
  Contributo in Atti di Convegno (Proceeding)
• 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
• Zammataro, Matteo; Falabino, Matteo; Abrate, Nicolo; Carta, Mario; Tomatis, Daniele (2024)
  A weight window approach for dose rate calculations in Lead-cooled Fast Reactors with OpenMC. In: 2024 Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo, SNA + MC 2024, Paris, 20-24 Ottobre 2024, pp. 1-10. ISSN 2100-014X
  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)
• 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)