Study of Online Operation Hazard Analysis Method of Nuclear Power Plant
-
摘要: 为了在线评估操纵员的操纵行为是否存在危害性,以避免人因失误、确保核动力装置安全运行,探讨了一种基于系统目标-功能模型的操纵危害分析方法,该方法根据核动力装置运行参数确定目标和功能状态,并根据目标-功能之间的因果依存关系定性推理分析操纵行为对系统目标的影响。研究结果表明,所提出的方法可以提示操纵员操纵动作对特定系统目标和功能的潜在危害性后果,方法鲁棒性好、实时性高,有助于减少和避免人因失误。Abstract: In order to online evaluate whether the operator’s operational actions is harmful, so as to avoid human error and ensure the safe operation of nuclear power plant, an operation hazard analysis method based on system goal-function model is presented, which determines the goal and function state according to the operation parameters of nuclear power plant. According to the cause-effect dependency between goal and function, qualitative reasoning is used to analyze the effects of operational actions on system goals. The results show that the proposed method can prompt the potential harmful consequences of the operator's operational actions on the specific system goals and functions. The method has good robustness and high real-time performance, and is helpful to reduce and avoid human errors.
-
Key words:
- Nuclear power plant /
- Hazard analysis /
- Functional modeling /
- Cause-effect analysis
-
表 1 核动力装置总体功能和安全功能目标
Table 1. Overall Functions and Safety Function Goals of Nuclear Power Plant
编号 说明 编号 说明 G1 冷却剂流量控制 So400 反应堆产热 G3 冷却剂压力控制 Si400 海水热阱导出 G4 冷却剂水位控制 Si401 海水热阱导出 G5 蒸汽压力控制 tr400 堆芯热量导出 G6 蒸汽发生器水位控制 tr401 冷却剂向蒸汽发生器传热 G7 余热排出 tr402 蒸汽发生器向冷凝器传热 G8 高压安注 tr403 冷凝器热量导出 G9 反应性控制 tr404 循环冷却水热量导出 G10 低压安注 St400 一回路储热 G11 冷凝器温度控制 St401 蒸汽发生器储热 St402 冷凝器储热 So—“源”(Source)功能;St—“存储”(Storage)功能; tr—“传输”功能;Si—“阱”(Sink)功能 表 2 操纵危害后果分类
Table 2. Classification for Hazard of Operation
分类 当前目标监测
状态目标预测
状态目标状态的
趋势变化操纵预警
提示1 H H ↓ 危害操作动作 2 M H ↓ 危害操作动作 3 L H ↑ 缓解操作动作 4 H L ↑ 缓解操作动作 5 M L ↓ 危害操作动作 6 L L ↓ 危害操作动作 -
[1] BAYBUTT P. On the need for system-theoretic hazard analysis in the process industries[J]. Journal of Loss Prevention in the Process Industries, 2021(69): 104356. doi: 10.1016/j.jlp.2020.104356 [2] YANG M, ZHANG Z J. Study on quantitative reliability analysis by multilevel flow models for nuclear power plants[J]. Nuclear Power Engineering, 2011, 32(4): 72-76. [3] LIND M. Reasoning about causes and consequences in mulitlevel flow models[C]//Advances in Safety, Reliability and Risk Management-Proceedings of the European Safety and Reliability Conference, ESREL 2011. France: Troyes, 2012.