Probabilistic Safety Analysis and Risk-Based Inspection of nuclear research reactors: state-of-the-art and implementation proposal

Documenti analoghi

• A simulation model for capacity planning of nuclear fuel plants for research reactors
  di: Miguel L. N. Negro
  Pubblicazione: (2021)
• Design of a digital system for operational parameters simulation of IPR-R1 Triga nuclear research reactor
  di: Aldo M. F. Lage
  Pubblicazione: (2019)
• Monitoring of Coolant Flow Rate and Velocity in the Hot Channel of the IPR-R1 TRIGA Reactor Core
  di: Amir Zacarias Mesquita
  Pubblicazione: (2010)
• Human factors engineering and participatory design in theproject of a nuclear research reactor control center
  di: Larissa Pereira Farias
  Pubblicazione: (2021)
• Human factors engineering and participatory design in the project of a nuclear research reactor control centre
  di: L. P. Farias
  Pubblicazione: (2019)