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In protection function design of nuclear power reactor, each reactor safety function should correspond to at least one primary protection line for each initiating fault. Besides, diverse protection lines are also demanded so as to meet the requirement of redundancy and diversity, which improves the reliability and protection function of the reactor system. In this study, methodology of diverse protection design and analysis is put forward, including the following process: identification of initiating faults, categorization and classification of safety function, determination of primary protection lines, determination of diverse protection lines, demonstration of sufficiency and validity, and improvement measure for the non-conformance. The design and analysis of diverse protection lines are carried out for typical reactivity fault in DBC-2. Fault schedule is produced to systematically present the primary protection line for design basis and diverse protection lines for DBC-2 reactivity faults. Based on the analysis of fault sequences characteristics and safety functions, the reactor trip protection functions of each reactivity fault are configured with diverse protection lines under three failure types: sensor failure, instrument control platform failure and mechanical system failure. A bounding case selection process on the basis of the faults and diverse protection lines is performed to determine the penalizing sequences considering the number of protection lines. Further quantitative analyses against acceptance criteria are performed for the identified bounding cases, which proves the diverse protection lines are sufficient to guarantee the reactor safety. Thus the validity of diverse protection lines provided in the fault schedule is demonstrated. This study establishes a methodology of diverse protection analysis, which presents an auditable link between initiating faults considered in the design and requirements to be applied to safety measures of nuclear power plant. It provides reference and supporting for optimization of diverse protection and continuous improvement of reactor system design.

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Research on Diverse Protection of Typical Reactivity Faults in DBC-2 of HPR1000

  • 会议论文

  • 发表日期：

    2026年

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  • Yingjie Feng,
  • Kaiwen Liang,
  • Yuting Wu,
  • Kun Xiong

摘要

In protection function design of nuclear power reactor, each reactor safety function should correspond to at least one primary protection line for each initiating fault. Besides, diverse protection lines are also demanded so as to meet the requirement of redundancy and diversity, which improves the reliability and protection function of the reactor system. In this study, methodology of diverse protection design and analysis is put forward, including the following process: identification of initiating faults, categorization and classification of safety function, determination of primary protection lines, determination of diverse protection lines, demonstration of sufficiency and validity, and improvement measure for the non-conformance. The design and analysis of diverse protection lines are carried out for typical reactivity fault in DBC-2. Fault schedule is produced to systematically present the primary protection line for design basis and diverse protection lines for DBC-2 reactivity faults. Based on the analysis of fault sequences characteristics and safety functions, the reactor trip protection functions of each reactivity fault are configured with diverse protection lines under three failure types: sensor failure, instrument control platform failure and mechanical system failure. A bounding case selection process on the basis of the faults and diverse protection lines is performed to determine the penalizing sequences considering the number of protection lines. Further quantitative analyses against acceptance criteria are performed for the identified bounding cases, which proves the diverse protection lines are sufficient to guarantee the reactor safety. Thus the validity of diverse protection lines provided in the fault schedule is demonstrated. This study establishes a methodology of diverse protection analysis, which presents an auditable link between initiating faults considered in the design and requirements to be applied to safety measures of nuclear power plant. It provides reference and supporting for optimization of diverse protection and continuous improvement of reactor system design.