Dynamic Event Tree Analysis of SGTR Accidents Considering HRA

Abstract The development of nuclear power is of significant importance in meeting the growing energy demands. The ongoing trend With a paramount Emphasis if safety is evident. Steam generator tube rupture (SGTR) accidents, characterized by a relatively high frequency and demanding operational requirements for operators, often involve simplified modeling of human factors in dynamic event tree (DET) method. This approach may struggle to depict the impact of operator error probability on DET sequence probabilities under different scenarios. A suitable human reliability analysis (HRA) is crucial for a more accurate assessment of system safety. This paper uses the DET method and standardized plant analysis risk-human reliability analysis (SPAR-H) method to analyze the SGTR accident of the CPR1000 unit, by calculating the operator’s maximum allowable time in different DET sequence scenarios, and studies the impact of extending the maximum allowable time of operator operation on human error probability (HEP) under different DET sequence scenarios, and addresses the limitations of simplified operator modeling in DET method. Analyzing DET sequence probabilities from a more realistic perspective demonstrates the advantages of incorporating SPAR-H for human reliability analysis within the DET method. The work is valuable for nuclear safety assessment.