Corso di laurea magistrale

• Radiation protection and safety of nuclear plants. A.A. 2023/24, INGEGNERIA ENERGETICA E NUCLEARE. Collaboratore del corso
• Fuel cycle, waste and decommissioning. A.A. 2023/24, INGEGNERIA ENERGETICA E NUCLEARE. Collaboratore del corso

• Colliva, Francesco; Hattab, Federico; Siriano, Simone; Ferrero, Gabriele; Meschini, ... (2024)
  Conceptual design and supporting analysis of a double wall heat exchanger for an ARC-class fusion reactor Primary cooling system. In: FUSION ENGINEERING AND DESIGN, vol. 201. ISSN 0920-3796
  Contributo su Rivista
• Delaporte-Mathurin, R.; Dark, J.; Ferrero, G.; Hodille, E. A.; Kulagin, V.; Meschini, S. (2024)
  FESTIM: An open-source code for hydrogen transport simulations. In: INTERNATIONAL JOURNAL OF HYDROGEN ENERGY, vol. 63, pp. 786-802. ISSN 0360-3199
  Contributo su Rivista
• Ledda, Federico; Pettinari, Davide; Ferrero, Gabriele; Hartwig, Zachary; Laviano, ... (2024)
  3D neutronic analysis on compact fusion reactors: PHITS-OpenMC cross-comparison. In: FUSION ENGINEERING AND DESIGN, vol. 202. ISSN 0920-3796
  Contributo su Rivista
• Ferrero, Gabriele; Meschini, Samuele; Testoni, Raffaella; Zucchetti, Massimo (2023)
  Exploration of ARC-class reactor vessel and divertor cooling system. In: FUSION ENGINEERING AND DESIGN, vol. 192. ISSN 0920-3796
  Contributo su Rivista
• Ferrero, Gabriele; Testoni, Raffaella; Zucchetti, Massimo (2023)
  Impact Assessment of Radiative Heat Transport in ARC-Class Reactor FLiBe Liquid Immersion Blanket. In: NUCLEAR SCIENCE AND ENGINEERING, pp. 1-16. ISSN 0029-5639
  Contributo su Rivista
• Ferrero, Gabriele; Meschini, Samuele; Testoni, Raffaella (2022)
  A preliminary CFD and Tritium transport analysis for ARC blanket. In: FUSION SCIENCE AND TECHNOLOGY, vol. 78, pp. 617-630. ISSN 1943-7641
  Contributo su Rivista