Published November 2015 | Version v1
Journal article

System assessment of an FPGA-based RPS for ABWR nuclear power plant

  • 1. Department of Engineering and System Science, National TsingHua University, No. 101, Section 2, Kung-Fu Road, Hsinchu City, 30013, Taiwan (China)
  • 2. Institute of Nuclear Engineering and Science, National TsingHua University, No. 101, Section 2, Kung-Fu Road, Hsinchu City, 30013, Taiwan (China)

Description

Highlights: •A diverse implementation is achieved during the design of the FPGA-based RPS. •The simulation results show that FPGA-based RPS is a practical design approach for LMNPP. •Sensitivity study of PRA shows that RPS combined with ARI contributes significant influence on CDF of LMNPP. •Software-free FPGA-based nuclear safety system is an easily alternative approach for modernization of NPP analog systems. -- Abstract: The instrumentation and control (I&C) systems for the Lungmen nuclear power plant (LMNPP) are fully digitized based on microprocessor and software technology, and extensively utilize multiplexing networks. That is, undetectable software faults and common cause failures due to software errors may occur, and that will defeat the redundancy of a nuclear power plant (NPP). A diverse backup implementation for the digital I&C systems is an important means to defense against undetectable software faults. This paper presents system assessment of a quad-redundant reactor protection system (RPS) design for an Advanced Boiling Water Reactor (ABWR) by utilizing the field programmable gate array (FPGA) technology. The FPGA-based RPS has been assessed by using a full-scope engineering simulator for the LMNPP. Accident scenarios and abnormal conditions are inserted into the engineering simulator in order to activate the function of the FPGA-based RPS. In this study, conceptual design of the proposed quad-redundant FPGA-based RPS, including preliminary hardware architecture, software design and system assessment will be presented. The results demonstrate that the FPGA-based RPS system is a practical approach to implement a diverse backup for the digital I&C system of nuclear power plant applications. Also, the sensitivity study of probabilistic risk assessment (PRA) shows that RPS combined with ARI (Alternative Rod Insertion) contributes significant influence on the core damage frequency (CDF) calculation of LMNPP. The PRA sensitivity study is independent of the RPS technology.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.pnucene.2015.05.010

Additional details

Identifiers

DOI
10.1016/j.pnucene.2015.05.010;
PII
S0149197015300032;

Publishing Information

Journal Title
Progress in Nuclear Energy
Journal Volume
85
Journal Page Range
p. 44-55
ISSN
0149-1970

Optional Information

Notes
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