Extended cognitive reliability and error analysis method for advanced control rooms of nuclear power plants

被引:2
|
作者
Zhang, Xiaodan [1 ]
Yan, Shengyuan [1 ]
Liu, Xin [1 ]
机构
[1] Harbin Engn Univ, Coll Mech & Elect Engn, Harbin 150001, Peoples R China
关键词
Human reliability analysis; The extended CREAM; The interval 2-tuple linguistic model; Human error probability; DEPENDENCE ASSESSMENT; CREAM MODEL; FUZZY; QUANTIFICATION; TASKS;
D O I
10.1016/j.net.2024.03.044
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
This study proposes a modified extended cognitive reliability and error analysis method (CREAM) for achieving a more accurate human error probability (HEP) in advanced control rooms. The traditional approach lacks failure data and does not consider the common performance condition (CPC) weights in different cognitive functions. The modified extended CREAM decomposes tasks using a method that combines structured information analysis (SIA) and the extended CREAM. The modified extended CREAM performs the weight analysis of CPCs in different cognitive functions, and the weights include cognitive, correlative, and important weights. We used the extended CREAM to obtain the cognitive weight. We determined the correlative weights of the CPCs for different cognitive functions using the triangular fuzzy decision-making trial and evaluation laboratory (TF-DEMATEL), and evaluated the importance weight of CPCs based on the interval 2-tuple linguistic approach and ensured the value of the importance weight using the entropy method in the different cognitive functions. Finally, we obtained the comprehensive weights of the different cognitive functions and calculated the HEPs. The accuracy and sensitivity of the modified extended CREAM were compared with those of the basic CREAM. The results demonstrate that the modified extended CREAM calculates the HEP more effectively in advanced control rooms.
引用
收藏
页码:3472 / 3482
页数:11
相关论文
共 50 条
  • [31] Human reliability qualitative analysis in nuclear power plant
    Dai Licao
    Zhang Li
    Huang Shudong
    PROGRESS IN SAFETY SCIENCE AND TECHNOLOGY, VOL 6, PTS A AND B, 2006, 6 : 581 - 584
  • [32] A framework to collect human reliability analysis data for nuclear power plants using a simplified simulator and student operators
    Park, Jooyoung
    Boring, Ronald L.
    Ulrich, Thomas A.
    Lew, Roger
    Lee, Sungheon
    Park, Bumjun
    Kim, Jonghyun
    RELIABILITY ENGINEERING & SYSTEM SAFETY, 2022, 221
  • [33] Study on a new framework of Human Reliability Analysis to evaluate soft control execution error in advanced MCRs of NPPs
    Jang, Inseok
    Kim, Ar Ryum
    Jung, Wondea
    Seong, Poong Hyun
    ANNALS OF NUCLEAR ENERGY, 2016, 91 : 92 - 104
  • [34] A method for systematically developing the knowledge base of reactor operators in nuclear power plants to support cognitive modeling of operator performance
    Zhao, Yunfei
    Smidts, Carol
    RELIABILITY ENGINEERING & SYSTEM SAFETY, 2019, 186 : 64 - 77
  • [35] CREAM-based communication error analysis method (CEAM) for nuclear power plant operators' communication
    Lee, Seung Min
    Ha, Jun Su
    Seong, Poong Hyun
    JOURNAL OF LOSS PREVENTION IN THE PROCESS INDUSTRIES, 2011, 24 (01) : 90 - 97
  • [36] Identifying a probe to visualize the variability of operating teams for supporting the human reliability analysis of nuclear power plants: An explanatory study
    Park, Jinkyun
    Vechgama, Wasin
    Shin, Seung Ki
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2025, 57 (02)
  • [37] Methodology for dynamic reliability assessment of team situation awareness of digital nuclear power plants
    Liu, Yahua
    Jin, Xiao
    Luo, Zhuhua
    Dai, Licao
    Liu, Zhen
    Li, Pengcheng
    PROGRESS IN NUCLEAR ENERGY, 2022, 144
  • [38] Methodology for dynamic reliability assessment of team situation awareness of digital nuclear power plants
    Liu, Yahua
    Jin, Xiao
    Luo, Zhuhua
    Dai, Licao
    Liu, Zhen
    Li, Pengcheng
    PROGRESS IN NUCLEAR ENERGY, 2022, 144
  • [39] Systematic Human Reliability Analysis (SHRA): A New Approach to Evaluate Human Error Probability (HEP) in a Nuclear Plant
    Di Bona, Gianpaolo
    Falcone, Domenico
    Forcina, Antonio
    Silvestri, Luca
    INTERNATIONAL JOURNAL OF MATHEMATICAL ENGINEERING AND MANAGEMENT SCIENCES, 2021, 6 (01) : 345 - 362
  • [40] Calculating nominal human error probabilities from the operation experience of domestic nuclear power plants
    Park, Jinkyun
    Kim, Yochan
    Jung, Wondea
    RELIABILITY ENGINEERING & SYSTEM SAFETY, 2018, 170 : 215 - 225