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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

Ranta, J., 2012, “The Current State of FPGA Technology in the Nuclear Domain,” Vuorimiehentie, Finland, VTT Technical Research.
International Electrotechnical Commission, 2004, Nuclear Power Plants—Instrumentation and Control Important for Safety—Software Aspects for Computer-Based Systems Performing Category B or C Functions, Geneva, Switzerland.
International Electrotechnical Commission, 2012, Nuclear Power Plants—Instrumentation and Control Important to Safety—Development of HDL-Programmed Integrated Circuits for Systems Performing Category A Functions, IEC, Geneva, Switzerland.
She, J., and Jiang, J., 2012, “Potential Improvement of CANDU NPP Safety Margins by Shortening the Response Time of Shutdown Systems Using FPGA Based Implementation,” Nucl. Eng. Des., 244(Mar.), pp. 43–51. 10.1016/j.nucengdes.2012.01.003
Naser, J., 2011, “Recommended Approaches and Design Criteria for Application of Field Programmable Gate Arrays in Nuclear Plant Instrumentation and Control,” EPRI, Palo Alto, CA.
McNelles, P., and Lu, L., 2013, “A Review of the Current State of FPGA Systems in Nuclear Instrumentation and Control,” Proceedings of the 21st International Conference on Nuclear Engineering, Chengdu, China.
Lu, J.-J., Chou, H.-P., and Wong, K.-W., 2010, “Conceptual Design of FPGA-based RPS for the Lungmen Nuclear Power Plant,” Proceedings of the 7th International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies (NPIC&HMIT), Las Vegas, NV, American Nuclear Society, La Grange Park, IL, pp. 944–953.
Huang, H., Chou, H., and Lin, C., 2012, “Design of a FPGA Based ABWR Feedwater Controller,” Nucl. Eng. Technol., 44(4), pp. 363–368. 0.5516/NET.04.2012.508
U.S. Nuclear Regulatory Commission, 2006, Criteria for Accident Monitoring Instrumentation for Nuclear Power Plants, U.S. Nuclear Regulatory Commission, Washington, DC.
IEEE Power and Energy Society, 2010, IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Generating Stations, IEEE Power and Energy Society, New York.
Canadian Standards Association, 2009, Requirements for Monitoring and Display of Nuclear Power Plant Safety Functions in the Event of an Accident, Canadian Standards Association, Mississauga, ON, Canada.
ASCA Inc., 2013, Dymonda 7.0 Software Guide, Redondo Beach, CA.
Aldemir, T., Guarro, S., Mandelli, D., et al. , 2010, “Probabilistic Risk Assessment Modeling of Digital Instrumentation and Control Using Two Dynamic Methodologies,” Reliab. Eng. Syst. Saf., 95(10), pp. 1011–1039. 10.1016/j.ress.2010.04.011
Aldemir, T., Stovsky, M. P., Miller, D. W., et al. , 2007, Dynamic Reliability Modeling of Digital Instrumentation and Control Systems for Nuclear Reactor Probabilistic Risk Assessments, U.S. Nuclear Regulatory Commission, Washington, DC.
Aldemir, T., Miller, D. W., Stovsk, M., et al. , 2007, “Methodologies for the Probabilistic Risk Assessment of Digital Reactor Protection and Control Systems,” Nucl. Technol., 159(2), pp. 167–191.
Authen, S., and Holmberg, J.-E., 2012, “Reliability Analysis of Digital Systems in a Probabilistic Risk Analysis for Nuclear Power Plants,” Nucl. Eng. Technol., 44(5), pp. 471–482. 10.5516/NET.03.2012.707
Garett, C., Guarro, S., Apostolakis, G., 1995, “The Dynamic Flowgraph Methodology for Assessing the Dependability of Embedded Software Systems,” IEEE Trans. Syst. Man Cybern., 25(5), pp. 824–840. 10.1109/21.376495
McNelles, P., and Lu, L., 2014, “Lab-Scale Design, Demonstration and Safety Assessment of an FPGA-based Post-Accident Monitoring System for Westinghouse AP1000 Nuclear Power Plants,” Proceedings of the 22nd International Conference on Nuclear Engineering, Prague, American Society of Mechanical Engineers, New York, NY.

Figures

Grahic Jump Location
Fig. 1

General PAMS subsystem DFM model

Grahic Jump Location
Fig. 2

General logic DFM model

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