Abstract
A signal validation methodology to improve the reliability of the information displayed to the operator of a nuclear power plant is presented. The general design methodology is developed and then applied to the steam generator and feedwater subsystem of a typical pressurized water reactor. Using steady-state and transient simulations of this subsystem, including realistic additive sensor noise, the developed algorithm successfully isolates a variety of injected sensor faults and demonstrates its inherent capability to isolate common-mode sensor failures and plant component failures.
| Original language | English (US) |
|---|---|
| Pages (from-to) | 24-29 |
| Number of pages | 6 |
| Journal | Journal of Dynamic Systems, Measurement and Control, Transactions of the ASME |
| Volume | 105 |
| Issue number | 1 |
| DOIs | |
| State | Published - Mar 1983 |
All Science Journal Classification (ASJC) codes
- Control and Systems Engineering
- Information Systems
- Instrumentation
- Mechanical Engineering
- Computer Science Applications