Correlating hardware fault detection information from distributed control systems to isolate and diagnose a fault in pressurised water reactors
Creators
- 1. North West University, School for Mechanical and Nuclear Engineering, Hoffman Street, North West Potchefstroom 2530 (South Africa)
Description
Highlights: ► Attempt was to use available resources at a nuclear plant in a value added fashion. ► Includes plant measurement data and plant training and engineering simulator capabilities. ► Correlating fault detection data for systems to develop of a deterministic fault identifications system. ► After implementing a host of data manipulation algorithms, the results provided more information on the fault than expected. - Abstract: Early fault identification systems enable detecting and diagnosing early onset faults or fault causes which allow maintenance planning on the equipment showing signs of deterioration or failure. This includes valve and leaks and small cracks in steam generator tubes usually detected by means of ultrasonic inspection. We have shown (Cilliers and Mulder, 2012) that detecting faults early during transient operation in NPPs is possible when coupled with a reliable reference to compare plant measurements with during transients. The problem introduced by the distributed application of control systems operating independently to keep the plant operating within the safe operating boundaries was solved by re-introducing the fault information it into the measurement data, thereby improving plant diagnostic performance. This paper introduces the use of improved fault detection information received from all distributed systems in the plant control system and correlating the information to not only detect the fault but also to diagnose it based on the location and magnitude of the fault cause
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2012.10.020Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2012.10.020;
- PII
- S0306-4549(12)00420-3;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 54
- Journal Page Range
- p. 91-103
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 45112205
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- ALGORITHMS; CRACKS; DETECTION; FAILURES; IDENTIFICATION SYSTEMS; LEAKS; NUCLEAR POWER PLANTS; REACTOR CONTROL SYSTEMS; REACTOR MAINTENANCE; SIMULATORS; STEAM GENERATORS; TUBES; ULTRASONIC TESTING; VALVES
- Descriptors DEC
- ACOUSTIC TESTING; ANALOG SYSTEMS; BOILERS; CONTROL EQUIPMENT; CONTROL SYSTEMS; EQUIPMENT; FLOW REGULATORS; FUNCTIONAL MODELS; MAINTENANCE; MATERIALS TESTING; MATHEMATICAL LOGIC; NONDESTRUCTIVE TESTING; NUCLEAR FACILITIES; POWER PLANTS; TESTING; THERMAL POWER PLANTS; VAPOR GENERATORS
Optional Information
- Copyright
- Copyright (c) 2012 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.