Research

  • PRA(Probabilistic Risk Assessment)
    -Nuclear Power Plant System Analysis (L1 PRA)
    Severe Accident Progression Analysis (L2 PRA)
    Consequence Analysis (L3 PRA)
    -Multi-unit PRA (MUPRA)

-Improving the safety design of nuclear power plants and improving the safety of nuclear power
plants by deriving severe accident scenarios and identifying vulnerabilities of nuclear power plants

-Development of Nuclear Safety Regulation Technology

  • PRA Framework and Codes

  • Level 1 PRA

-Systematically analyze the operation of major systems, including operator actions taken to mitigate or terminate accidents according to the progress of the accident and the necessary safety systems, to evaluate the circumstances and frequency of core damage accidents

-Identify weaknesses in plant design and operation, suggest improvement measures

  • Source Term Analysis for Severe Accidents using MELCOR

-Effects of severe accident phenomena, behavior of the mitigation system, and operator actions that
may occur after core damage are analyzed

-Uses MELCOR codes that can comprehensively address the hydrothermal phenomena of severe
accidents and the release of fission products


  • Level 2 Frequency Analysis

-After core damge, severe accident phenomena and behavior of radioactive materials in contatinment buildings are analyzed, the type and frequency of damage to containment buildings, and the amount and time of release of radioactive materials released to the environment are evaluated

  • Level 3 Consequence Analysis

-Analysis of public health and economic impacts caused by radioactive substances emitted to the environment in the event of a nuclear accident (MACCS)

-Risk assessment of nuclear power plants by combining the frequency of core damage, characteristics of containment damage, and public damage resulting from each stage of PRA

  • An Example of Site Data Using HEPRI Code