Reliability Modeling and Analysis of Reactor Protection System Based on FPGA

Zhang Dongliang; Zhang Kaiwen; Zhang Chaofan

doi:10.13832/j.jnpe.2021.05.0173

Volume 42 Issue 5

Sep. 2021

Turn off MathJax

Article Contents

Article Navigation > Nuclear Power Engineering > 2021 > 42(5): 173-177

Zhang Dongliang, Zhang Kaiwen, Zhang Chaofan. Reliability Modeling and Analysis of Reactor Protection System Based on FPGA[J]. Nuclear Power Engineering, 2021, 42(5): 173-177. doi: 10.13832/j.jnpe.2021.05.0173

Citation:

Zhang Dongliang, Zhang Kaiwen, Zhang Chaofan. Reliability Modeling and Analysis of Reactor Protection System Based on FPGA[J]. Nuclear Power Engineering, 2021, 42(5): 173-177. doi: 10.13832/j.jnpe.2021.05.0173

Citation:

PDF( 2535 KB)

Reliability Modeling and Analysis of Reactor Protection System Based on FPGA

doi: 10.13832/j.jnpe.2021.05.0173

1.
Shanghai Key Laboratory of Power Station Automation Technology, Shanghai, 200090, China
2.
College of Automation Engineering, Shanghai University of Electric Power, Shanghai, 200090, China

Received Date: 2020-07-24
Rev Recd Date: 2020-09-23
Publish Date: 2021-09-30

Abstract

Abstract

In order to establish a reactor protection system reliability model based on the field programmable gate array (FPGA) to provide effective analysis and verification methods for system safety, this study adopts the fault tree and stochastic Petri net (SPN) models to perform reliability modeling and analysis for the single channel of CANDU reactor shutdown system 1 (SDS1). The analysis by fault tree model provides the minimal cut set. With the top event probability taken as the system fault probability, and in consideration of the fault detection, maintenance and periodic testing, the probability of rejection of the system is obtained by the stochastic Petri net model simulation. The results show that both the fault tree and state space representation are limited to a certain extent, while the stochastic Petri net can reflect the impact of fault detection and periodic tests on the reactor protection system, dynamically present the system reliability, and avoid the problem of state space explosion. Therefore, the stochastic Petri net model established in this study is suitable for the reliability modeling of the reactor protection system.
- Reactor protection system,
- FPGA,
- Reliability,
- Fault tree,
- SPN

FullText(HTML)

References(10)

References

[1]	NRC. Review guidelines for field-programmable gate arrays in nuclear power plant safety system: NRC-7006[R]. USA: NRC, 2009.
[2]	EPRI. Guidelines on the use of field programmable gate arrays in nuclear power plant I&C systems: EPRI-2009[R]. USA: Electric Power Research Institute, 2009.
[3]	EPRI. Recommended approached and design criteria for application of field programmable gate arrays in nuclear power plant instrumentation and control systems: EPRI-2011[R]. USA: Electric Power Research Institute, 2011.
[4]	NRC. Review guidelines for field-programmable gate arrays in nuclear power plant safety systems: NRC-2010a[R]. USA: NRC, 2010.
[5]	SHE J, JIANG J. On the speed of response of an FPGA-based shutdown system in CANDU nuclear power plants[J]. Nuclear Engineering and Design, 2011, 246(6): 2290-2287.
[6]	MCNELLES P, ZENG Z C, RENGANATHAN G, et al. A comparison of fault trees and the dynamic flowgraph methodology for the analysis of FPGA-based safety systems part 1: reactor trip logic loop reliability analysis[J]. Reliability Engineering & System Safety, 2016(153): 135-150.
[7]	MA Z, YOSHIKAWA H, YANG M. Module level reliability performance evaluation of digital reactor protection system considering the repair and common cause failure[J]. Annals of Nuclear Energy, 2017(110): 805-817.
[8]	曹枭虓,熊华胜,郭超,等. 反应堆保护系统动态可靠性建模与分析[J]. 自动化仪表,2019, 40(6): 6-10.
[9]	JUNG J, AHMED I. Development of field programmable gate array-based reactor trip functions using systems engineering approach[J]. Nuclear Engineering and Design, 2016, 48(4): 1047-1057.
[10]	王浩. 基于FPGA的数字化仪控系统动态可靠性评价[D]. 保定: 华北电力大学, 2018.