Development of RPS Trip Logic Based on PLD Technology

Choi, Jong Gyun; Lee, Dong Hoon

doi:10.5516/net.04.2011.004

Cited by 11 publications

(5 citation statements)

References 3 publications

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“…The irregular situations that cause reactor trips are called emergency situations in the nuclear field. After the indication of a reactor trip, operators in the main control room perform emergency operating procedures to mitigate the accident consequences that caused the plant parameters to exceed the reactor protection system set points or engineered safety feature set points, or other established limits [32]. According to the relevant emergency operating procedure, operators cope with the symptoms of the early trip phase and diagnose the accident.…”

Section: Operator Actions In Emergency Situationsmentioning

confidence: 99%

Consistency Index-Based Sensor Fault Detection System for Nuclear Power Plant Emergency Situations Using an LSTM Network

Choi

Lee

2020

Sensors

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A nuclear power plant (NPP) consists of an enormous number of components with complex interconnections. Various techniques to detect sensor errors have been developed to monitor the state of the sensors during normal NPP operation, but not for emergency situations. In an emergency situation with a reactor trip, all the plant parameters undergo drastic changes following the sudden decrease in core reactivity. In this paper, a machine learning model adopting a consistency index is suggested for sensor error detection during NPP emergency situations. The proposed consistency index refers to the soundness of the sensors based on their measurement accuracy. The application of consistency index labeling makes it possible to detect sensor error immediately and specify the particular sensor where the error occurred. From a compact nuclear simulator, selected plant parameters were extracted during typical emergency situations, and artificial sensor errors were injected into the raw data. The trained system successfully generated output that gave both sensor error states and error-free states.

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Section: Operator Actions In Emergency Situationsmentioning

confidence: 99%

Consistency Index-Based Sensor Fault Detection System for Nuclear Power Plant Emergency Situations Using an LSTM Network

Choi

Lee

2020

Sensors

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“…When developing a new I&C system in Korean nuclear power plants with PLCs (Programmable Logic Controllers) [1], [2], the correctness and safety demonstration of the FBD-to-C [3] and C-to-PLC translators was strongly requested by regulation authorities for approving the operation of the I&C system [4]. We are now developing an I&C system [5] with FPGAs (Field Programmable Logic Controller) [6] in place of PLCs, due to the increasing maintenance cost of PLCs and the higher performance of FPGAs.…”

Section: Introductionmentioning

confidence: 99%

A Technique for Demonstrating Safety and Correctness of Program Translators: Strategy and Case Study

Yoo

Choi

Lee

2014

2014 IEEE International Symposium on Software Reliability Engineering Workshops

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The safety and correctness demonstration of program translators plays a critical role in software certification of digital I&C (Instrumentation & Control) systems in nuclear power plants. This paper proposes a strategy for the demonstration of the FBDtoVerilog translator, which translates FBD programs into Verilog programs to synthesize FPGAs. It uses safety case to explain the strategy precisely and also implemented several supporting tools to derive evidences efficiently. A case study of a Korean nuclear power plant found the efficiency of the proposed demonstration strategy and supporting tools.

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“…[Example System III & IV] start from Verilog and VHDL programs, respectively, for an experimental programmable logic device (PLD)-based RPS BP [2] in Korea. They consist of 18 shutdown logics as commercial RPS BPs, but are experimental systems with fundamental functionalities.…”

Section: Case Studymentioning

confidence: 99%

“…This paper summarizes all the different case studies that we performed with several extracted reactor protection systems (RPS) examples [2,[12][13][14].…”

Section: Introductionmentioning

confidence: 99%

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NuDE 2.0: A Formal Method-based Software Development, Verification and Safety Analysis Environment for Digital I&Cs in NPPs

Kim¹,

Lee²,

Jung³

et al. 2017

Journal of Computing Science and Engineering

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NuDE 2.0 (Nuclear Development Environment 2.0) is a formal-method-based software development, verification and safety analysis environment for safety-critical digital I&Cs implemented with programmable logic controller (PLC) and field-programmable gate array (FPGA). It simultaneously develops PLC/FPGA software implementations from one requirement/design specification and also helps most of the development, verification, and safety analysis to be performed mechanically and in sequence. The NuDE 2.0 now consists of 25 CASE tools and also includes an in-depth solution for indirect commercial off-the-shelf (COTS) software dedication of new FPGA-based digital I&Cs. We expect that the NuDE 2.0 will be widely used as a means of diversifying software design/implementation and model-based software development methodology.

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Development of RPS Trip Logic Based on PLD Technology

Cited by 11 publications

References 3 publications

Consistency Index-Based Sensor Fault Detection System for Nuclear Power Plant Emergency Situations Using an LSTM Network

Consistency Index-Based Sensor Fault Detection System for Nuclear Power Plant Emergency Situations Using an LSTM Network

A Technique for Demonstrating Safety and Correctness of Program Translators: Strategy and Case Study

NuDE 2.0: A Formal Method-based Software Development, Verification and Safety Analysis Environment for Digital I&Cs in NPPs

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