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Formal Software Requirements Specification for Digital Reactor Protection Systems  

유준범 (KAIST 전자전산학과)
차성덕 (KAIST 전자전산학)
김창회 (한국원자력연구소 계측제어인간공학연구)
오윤주 (LG전자 UMTS 연구소 차세대단말팀)
Publication Information
Journal of KIISE:Software and Applications / v.31, no.6, 2004 , pp. 750-759 More about this Journal
Abstract
The software of the nuclear power plant digital control system is a safety-critical system where many techniques must be applied to it in order to preserve safety in the whole system. Formal specifications especially allow the system to be clearly and completely specified in the early requirements specification phase therefore making it a trusted method for increasing safety. In this paper, we discuss the NuSCR, which is a qualified formal specification method for specifying nuclear power plant digital control system software requirements. To investigate the application of NuSCR, we introduce the experience of using NuSCR in formally specifying the plant protection system's software requirements, which is presently being developed at KNICS. Case study that shows that the formal specification approach NuSCR is very much qualified and specialized for the nuclear domain is also shown.
Keywords
formal method; software requirements specification; nuclear power plants protection system;
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