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Technical Brief

Dynamic Flowgraph Methodology Assessment of an FPGA-Based Postaccident Monitoring System for Westinghouse AP1000 Nuclear Power Plants

[+] Author and Article Information
Phillip McNelles

Mem. ASME
Faculty of Energy Systems and Nuclear Science,
University of Ontario Institute of Technology,
2000 Simcoe Street North, Oshawa, Ontario L1J 7K4, Canada
e-mail: phillip.mcnelles@gmail.com

Lixuan Lu

Faculty of Energy Systems and Nuclear Science,
University of Ontario Institute of Technology,
2000 Simcoe Street North, Oshawa, Ontario L1J 7K4, Canada
e-mail: lixuan.lu@uoit.ca

Marc-James Abi-Jaoude

Sartrex Power Control Systems,
222 Snidercroft Road, Concord, Ontario L4K 2K1, Canada
e-mail: mabijaoude@sartrex.ca

1Corresponding author.

Manuscript received August 18, 2014; final manuscript received December 28, 2014; published online May 20, 2015. Assoc. Editor: John F. P. de Grosbois.

ASME J of Nuclear Rad Sci 1(3), 034501 (May 20, 2015) (4 pages) Paper No: NERS-14-1035; doi: 10.1115/1.4029591 History: Received August 18, 2014; Accepted May 20, 2015; Online May 20, 2015

A field-programmable gate array (FPGA) is a type of integrated circuit that is programmed after being manufactured. These FPGA-based systems are considered to be viable alternatives to replace many obsolete instrumentation and control (I&C) systems that are used in nuclear plants. This paper describes an FPGA-based lab-scale implementation of a postaccident monitoring system (PAMS), for a Westinghouse AP1000 reactor. This system will monitor vital parameters in the event of a serious reactor accident. The system reliability was analyzed using the dynamic flowgraph methodology (DFM). DFM was applied to fine-tune the design parameters by determining the potential causes of faults in the design.

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References

Figures

Grahic Jump Location
Fig. 1

General PAMS subsystem DFM model

Grahic Jump Location
Fig. 2

General logic DFM model

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