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.
Issue Section:
Technical Brief
References
1.
Ranta
, J.
, 2012
, “The Current State of FPGA Technology in the Nuclear Domain
,” Vuorimiehentie, Finland, VTT Technical Research.2.
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
.3.
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
.4.
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.2012.01.0035.
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.6.
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
.7.
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
.8.
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.04.2012.5089.
U.S. Nuclear Regulatory Commission
, 2006
, Criteria for Accident Monitoring Instrumentation for Nuclear Power Plants
, U.S. Nuclear Regulatory Commission
, Washington, DC
.10.
IEEE Power and Energy Society
, 2010
, IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Generating Stations
, IEEE Power and Energy Society
, New York
.11.
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
.12.
ASCA Inc.
, 2013
, Dymonda 7.0 Software Guide
, Redondo Beach, CA
.13.
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.2010.04.01114.
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
.15.
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
.16.
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.03.2012.70717.
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
.10.1109/21.37649518.
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
.Copyright © 2015 by ASME
You do not currently have access to this content.