A formal software requirements specification method for digital nuclear plant protection systems

Authors:
Junbeom Yoo;Taihyo Kim;Sungdeok Cha;Jang-Soo Lee;Han Seong Son
Affiliations:
Department of Electrical Engineering and Computer Science, Korea Advanced Institute of Science and Technology (KAIST) and AITrc/SPIC, 373-1, Kusong-dong, Yusong-gu, Taejon 305701, South Korea;Department of Electrical Engineering and Computer Science, Korea Advanced Institute of Science and Technology (KAIST) and AITrc/SPIC, 373-1, Kusong-dong, Yusong-gu, Taejon 305701, South Korea;Department of Electrical Engineering and Computer Science, Korea Advanced Institute of Science and Technology (KAIST) and AITrc/SPIC, 373-1, Kusong-dong, Yusong-gu, Taejon 305701, South Korea;Korea Atomic Energy Research Institute (KAERI), MMIS team, 150, Deokjin-dong, Yusong-gu, Taejon, South Korea;Korea Atomic Energy Research Institute (KAERI), MMIS team, 150, Deokjin-dong, Yusong-gu, Taejon, South Korea
Venue:
Journal of Systems and Software - Special issue: Automated component-based software engineering
Year:
2005

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Abstract

This article describes NuSCR, a formal software requirements specification method for digital plant protection system in nuclear power plants. NuSCR improves the readability and specifiability by providing graphical or tabular notations depending on the type of operations. NuSCR specifications can be formally analyzed for completeness, consistency, and against the properties specified in temporal logic. We introduce the syntax and semantics of NuSCR and demonstrate the effectiveness of the approach using reactor protection system, digital protection system being developed in Korea, as a case study.