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.2015.05.010Additional 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
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51027551
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTER CODES; NUCLEAR POWER PLANTS; PROBABILISTIC ESTIMATION; REACTOR PROTECTION SYSTEMS; RISK ASSESSMENT; SENSITIVITY ANALYSIS; SIMULATORS
- Descriptors DEC
- ANALOG SYSTEMS; CALCULATION METHODS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; FUNCTIONAL MODELS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Copyright © 2015 Elsevier Ltd. All rights reserved.