Dynamic Flowgraph Methodology Assessment of an FPGA-Based Postaccident Monitoring System for Westinghouse AP1000 Nuclear Power Plants-Reference-Cited by-同舟云学术

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

Published:2015-05-20 Issue:3 Volume:1 Page:
ISSN:2332-8983
Container-title:Journal of Nuclear Engineering and Radiation Science
language:en
Short-container-title:

Author:

McNelles Phillip¹,Lu Lixuan²,Abi-Jaoude Marc-James³

Affiliation:

1. 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:

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

3. Sartrex Power Control Systems, 222 Snidercroft Road, Concord, Ontario L4K 2K1, Canada e-mail:

Abstract

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.

Publisher

ASME International

Subject

Nuclear Energy and Engineering,Radiation

Link

http://asmedigitalcollection.asme.org/nuclearengineering/article-pdf/doi/10.1115/1.4029591/6065597/ners_1_3_034501.pdf

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