Abstract
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 real-time 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.
| Original language | English |
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| Title of host publication | 10th International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies, NPIC and HMIT 2017 |
| Publisher | American Nuclear Society |
| Pages | 1423-1431 |
| Number of pages | 9 |
| ISBN (Electronic) | 9781510851160 |
| State | Published - 2017 |
| Externally published | Yes |
| Event | 10th International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies, NPIC and HMIT 2017 - San Francisco, United States Duration: Jun 11 2017 → Jun 15 2017 |
Publication series
| Name | 10th International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies, NPIC and HMIT 2017 |
|---|---|
| Volume | 2 |
Conference
| Conference | 10th International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies, NPIC and HMIT 2017 |
|---|---|
| Country/Territory | United States |
| City | San Francisco |
| Period | 06/11/17 → 06/15/17 |
Funding
The work described in this paper was sponsored by the Advanced Reactor Technologies R&D program of the U.S. Department of Energy’s Office of Nuclear Energy. A portion of the work described in this paper was performed at the Pacific Northwest National Laboratory, managed by Battelle for the U.S. Department of Energy under DOE contract number DE-AC06-76RLO-1830. A part of the work described in this paper was performed at the Oak Ridge National Laboratory, managed by UT-Battelle for the U.S. Department of Energy. The work described in this paper was sponsored by the Advanced Reactor Technologies R&D program of the U.S. Department of Energy's Office of Nuclear Energy. A portion of the work described in this paper was performed at the Pacific Northwest National Laboratory, managed by Battelle for the U.S. Department of Energy under DOE contract number DE-AC06-76RLO-1830. A part of the work described in this paper was performed at the Oak Ridge National Laboratory, managed by UT-Battelle for the U.S. Department of Energy.
Keywords
- Predictive risk monitor
- Risk-informed decision making
- Supervisory control system
- Valve prognostics