Ricerca

Pubblicazioni IRIS

• Preliminary Thermal-hydraulic Analysis of Subcritical Fission Zone for Conceptual Test Blanket Module Driven by Fusion Neutrons
  Anno: 2026
• 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
• Plentiful Tritium generation by a FFHR to feed a fusion power plant with simplified blanket
  Anno: 2025
• Nuclear Reactor Physics and Operation: Neutronic Analysis for Nuclear Reactor Design
  Anno: 2025
• A review of strategies and challenges of super critical water-cooled reactor (SCWR) deployment and technology readiness assessment of a SCWR- SMR design
  Anno: 2025