Ricerca

Pubblicazioni IRIS

• Corrigendum to “ Plentiful Tritium generation by a FFHR to feed a fusion power plant with simplified blanket” [Fusion Engineering and Design 217 (2025) 115138]
  Anno: 2026
• Preliminary Thermal-hydraulic Analysis of Subcritical Fission Zone for Conceptual Test Blanket Module Driven by Fusion Neutrons
  Anno: 2026
• Preliminary Thermal-hydraulic Analysis of Proposed Simplified Test Blanket Module (TBM) as a Subcritical Reactor Driven by Fusion Neutrons
  Anno: 2025
• Nuclear Reactor Physics and Operation: Neutronic Analysis for Nuclear Reactor Design
  Anno: 2025
• Plentiful Tritium generation by a FFHR to feed a fusion power plant with simplified blanket
  Anno: 2025