Containment Analysis Package

CAP
  • Developed by FNC to analyze the thermal-hydraulic behavior of nuclear plant containment as the fourth barrier

  • Using state-of-art technique including 3-fields and 3-phases

  • Coupling with SPACE (System code independently developed in Korea)

  • Successfully licensed by NSSC (Nuclear Safety and Security Commission)


Applicable Fields
of CAP
  • Design pressure/temperature

  • ECCS efficiency

  • Subcompartment pressure

  • Long-term containment pressure and temperature

  • Hydrogen concentration


Utilization of
Severe Accident
Analysis Codes
  • Covering single-phase and two-phase thermal hydraulic analysis, accident analysis, and DEC analysis with RELAP, RETRAN, MARS, GOTHIC, and CFX

  • Application to design passive safety systems of NPP, such as PAFS (Passive Aux. Feedwater System) and PECCS (Passive Emergency Core Cooling System)