Journal of the Korean Society of Systems Engineering (시스템엔지니어링학술지)

The Korean Society of Systems Engineering (한국시스템엔지니어링학회)
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A Systems Engineering Approach to Ex-Vessel Cooling Strategy for APR1400 under Extended Station Blackout Conditions

  • Saja Rababah (Nuclear Engineering Department, KEPCO International Nuclear Graduate School) ;
  • Aya Diab (Nuclear Engineering Department, KEPCO International Nuclear Graduate School)
  • Received : 2023.07.02
  • Accepted : 2023.12.06
  • Published : 2023.12.31
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Abstract

Implementing Severe Accident Management (SAM) strategies is crucial for enhancing a nuclear power plant's resilience and safety against severe accidents conditions represented in the analysis of Station Blackout (SBO) event. Among these critical approaches, the In-Vessel Retention (IVR) through External Reactor Vessel Cooling (IVR-ERVC) strategy plays a key role in preventing vessel failure. This work is designed to evaluate the efficacy of the IVR strategy for a high-power density reactor APR1400. The APR1400's plant is represented and simulated under steady-state and transient conditions for a station blackout (SBO) accident scenario using the computer code, ASYST. The APR1400's thermal-hydraulic response is analyzed to assess its performance as it progresses toward a severe accident scenario during an extended SBO. The effectiveness of emergency operating procedures (EOPs) and severe accident management guidelines (SAMGs) are systematically examined to assess their ability to mitigate the accident. A group of associated key phenomena selected based on Phenomenon Identification and Ranking Tables (PIRT) and uncertain parameters are identified accordingly and then propagated within DAKOTA Uncertainty Quantification (UQ) framework until a statistically representative sample is obtained and hence determine the uncertainty bands of key system parameters. The Systems Engineering methodology is applied to direct the progression of work, ensuring systematic and efficient execution.

Keywords

Acknowledgement

This research was supported by the 2023 Research Fund of the KEPCO International Nuclear Graduate School (KINGS), Republic of Korea.

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