Integration and assessment of component health prognostics in supervisory control systems - 291
Creators
- 1. Pacific Northwest National Laboratory, Richland, WA (United States)
- 2. Oak Ridge National Laboratory, Oak Ridge, TN (United States)
Description
Enhanced risk monitors (ERMs) for active components in advanced reactor concepts use predictive estimates of component failure to update, in real time, predictive safety and economic risk metrics. These metrics have been shown to be capable of use in optimizing maintenance scheduling and managing plant maintenance costs. Integrating this information with plant supervisory control systems increases the potential for making control decisions that utilize realtime information on component conditions. Such decision making would limit the possibility of plant operations that increase the likelihood of degrading the functionality of one or more components while maintaining the overall functionality of the plant. ERM uses sensor data for providing real-time information about equipment condition for deriving risk monitors. This information is used to estimate the remaining useful life and probability of failure of these components. By combining this information with plant probabilistic risk assessment models, predictive estimates of risk posed by continued plant operation in the presence of detected degradation may be estimated. In this paper, we describe this methodology in greater detail, and discuss its integration with a prototypic software-based plant supervisory control platform. In order to integrate these two technologies and evaluate the integrated system, software to simulate the sensor data was developed, prognostic models for feedwater valves were developed, and several use cases defined. The full paper will describe these use cases, and the results of the initial evaluation. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park, IL (United States)
- Imprint Pagination
- 9 p.
Conference
- Title
- 10. International Conference on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies
- Acronym
- NPIC and HIMIT 2017
- Dates
- 11-15 Jun 2017
- Place
- San Francisco, CA (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 52075772
- Subject category
- S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FEEDWATER; METRICS; OPTIMIZATION; PROBABILISTIC ESTIMATION; REACTOR CONTROL SYSTEMS; REACTOR MAINTENANCE; REACTOR OPERATION; RISK ASSESSMENT; SENSORS; VALVES
- Descriptors DEC
- CALCULATION METHODS; CONTROL EQUIPMENT; CONTROL SYSTEMS; EQUIPMENT; FLOW REGULATORS; HYDROGEN COMPOUNDS; MAINTENANCE; OPERATION; OXYGEN COMPOUNDS; REACTOR LIFE CYCLE; REACTOR OPERATION; WATER
Optional Information
- Notes
- 21 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)