Reliability Analysis of the Passive Residual Heat Removal System for Large Advanced Pressurized Water Reactors
ID:68 View Protection:ATTENDEE Updated Time:2024-09-08 17:37:04 Hits:368 Oral Presentation

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Abstract
This paper focuses on the passive residual heat removal system of a typical large advanced pressurized water reactor, analyzing its design, performance, and reliability under station blackout conditions coupled with the failure of the auxiliary feedwater steam-driven pumps. The study employs modeling of passive safety systems and utilizes response surface methodology to evaluate system behavior during severe accident scenarios. Such comprehensive analysis contributes to ensuring the safe operation and advancement of nuclear power plants. The best-estimate program VITARS is used to analyze and calculate accident scenarios, with sensitivity analysis conducted based on preliminary thermal-hydraulic calculations to optimize parameter selection and simplify the response surface model structure, thereby streamlining the analysis process. An artificial neural network is employed as a surrogate model for complex thermal-hydraulic calculations, significantly improving analysis efficiency. The findings indicate that the passive residual heat removal system has zero failure probability under normal uncertainty ranges within 72 hours. Even under extreme conditions, such as delayed opening of the steam generator's safety valve, the system maintains reactor safety with a failure probability of only 0.035%.
Keywords
Passive residual heat removal system,Response surface,Artificial neural network
Speaker
Tianrui Li
Xi'an Jiaotong University

Submission Author
Tianrui Li Xi'an Jiaotong University
Ronghua Chen Xi'an Jiaotong University
Xinkun Xiao Xi'an Jiaotong University
Guoqing Lu Xi'an Jiaotong University
Shikang Chen Xi'an Jiaotong University
Wenxi Tian Xi'an Jiaotong University
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    Sep 23

    2024

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    Sep 25

    2024

  • Sep 24 2024

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