TY - JOUR
T1 - Integrating renewal process modeling with Probabilistic Physics-of-Failure
T2 - Application to Loss of Coolant Accident (LOCA) frequency estimations in nuclear power plants
AU - Sakurahara, Tatsuya
AU - O'Shea, Nicholas
AU - Cheng, Wen Chi
AU - Zhang, Sai
AU - Reihani, Seyed
AU - Kee, Ernie
AU - Mohaghegh, Zahra
N1 - Funding Information:
This material is based upon work supported by the U.S. Department of Energy under an Integrated University Program Graduate Fellowship. This research is partially supported by the U.S. Department of Energy , Office of Science , Office of Nuclear Energy University Program (NEUP), Reactor Concepts Research Development and Demonstration (RCRD&D) under Award #17-12614. Any opinions, findings, conclusions, or recommendations expressed in this publication are those of the authors and do not necessarily reflect the views of the Department of Energy, Office of Nuclear Energy. This work made use of the Illinois Campus Cluster, a computing resource that is operated by the Illinois Campus Cluster Program (ICCP) in conjunction with the National Center for Supercomputing Applications (NCSA) and is supported by funds from the University of Illinois at Urbana-Champaign . The authors would like to thank all members of the Socio-Technical Risk Analysis Laboratory ( http://soteria.npre.illinois.edu/ ) for their support and, especially, the undergraduate research assistants, Grant Schumock, for his support with the global sensitivity analysis, and John Beal, for his review of the paper.
Funding Information:
This material is based upon work supported by the U.S. Department of Energy under an Integrated University Program Graduate Fellowship. This research is partially supported by the U.S. Department of Energy, Office of Science, Office of Nuclear Energy University Program (NEUP), Reactor Concepts Research Development and Demonstration (RCRD&D) under Award #17-12614. Any opinions, findings, conclusions, or recommendations expressed in this publication are those of the authors and do not necessarily reflect the views of the Department of Energy, Office of Nuclear Energy. This work made use of the Illinois Campus Cluster, a computing resource that is operated by the Illinois Campus Cluster Program (ICCP) in conjunction with the National Center for Supercomputing Applications (NCSA) and is supported by funds from the University of Illinois at Urbana-Champaign. The authors would like to thank all members of the Socio-Technical Risk Analysis Laboratory (http://soteria.npre.illinois.edu/) for their support and, especially, the undergraduate research assistants, Grant Schumock, for his support with the global sensitivity analysis, and John Beal, for his review of the paper.
Publisher Copyright:
© 2019 Elsevier Ltd
PY - 2019/10
Y1 - 2019/10
N2 - Renewal process modeling is used for the failure prediction of hardware components under periodic maintenance. While most studies utilized data-driven approaches to estimate the input parameters for renewal process models, this paper initiates a line of research to integrate renewal process modeling with probabilistic models of underlying mechanisms associated with physical degradation and maintenance. At this stage of the research, the methodology integrates Markov modeling with Probabilistic Physics-of-Failure (PPoF) models of degradation, while maintenance is treated by a data-driven approach. This methodology is valuable to obtain a more accurate estimation of component reliability and availablity, especially when (i) components are highly reliable, and failure data are limited, (ii) historical data are unreliable due to changes in design, operation, and maintenance, or (iii) advanced technologies have emerged limiting operational data. The methodology explicitly incorporates the underlying spatiotemporal causes of failure into the renewal model, allowing to rank the criticality of causal factors to improve maintenance and mitigation strategies. Although the new methodology is applicable for component reliability and availability analysis in diverse industries, this paper demonstrates its value for estimating frequencies of a Loss-Of-Coolant Accident (LOCA), which is an initiating event in Probabilistic Risk Assessment (PRA) of Nuclear Power Plants (NPPs).
AB - Renewal process modeling is used for the failure prediction of hardware components under periodic maintenance. While most studies utilized data-driven approaches to estimate the input parameters for renewal process models, this paper initiates a line of research to integrate renewal process modeling with probabilistic models of underlying mechanisms associated with physical degradation and maintenance. At this stage of the research, the methodology integrates Markov modeling with Probabilistic Physics-of-Failure (PPoF) models of degradation, while maintenance is treated by a data-driven approach. This methodology is valuable to obtain a more accurate estimation of component reliability and availablity, especially when (i) components are highly reliable, and failure data are limited, (ii) historical data are unreliable due to changes in design, operation, and maintenance, or (iii) advanced technologies have emerged limiting operational data. The methodology explicitly incorporates the underlying spatiotemporal causes of failure into the renewal model, allowing to rank the criticality of causal factors to improve maintenance and mitigation strategies. Although the new methodology is applicable for component reliability and availability analysis in diverse industries, this paper demonstrates its value for estimating frequencies of a Loss-Of-Coolant Accident (LOCA), which is an initiating event in Probabilistic Risk Assessment (PRA) of Nuclear Power Plants (NPPs).
KW - Component reliability and availability
KW - Loss of Coolant Accident (LOCA)
KW - Maintenance work process model
KW - Probabilistic Physics-of-Failure (PPoF)
KW - Probabilistic Risk Assessment (PRA)
KW - Renewal process modeling
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U2 - 10.1016/j.ress.2019.04.032
DO - 10.1016/j.ress.2019.04.032
M3 - Article
AN - SCOPUS:85066478113
SN - 0951-8320
VL - 190
JO - Reliability Engineering and System Safety
JF - Reliability Engineering and System Safety
M1 - 106479
ER -