Formal verification method for nuclear I and C systems using ESDT and SMV in the software design phase
- 1. Dept. of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)
Description
As PLCs are widely used in the digital I and C systems of nuclear power plants (NPPs), the safety of PLC software has become the most important consideration. Software safety is an important property for safety critical systems, especially those in aerospace, satellite and nuclear power plants, whose failure could result in danger to human life, property or environment. It is recently becoming more important due to the increase in the complexity and size of safety critical systems. This research proposes a method to perform effective verification tasks on the traceability analysis and software design evaluation in the software design phase. In order to perform the traceability analysis between a Software Requirements Specification (SRS) written in a natural language and a Software Design Specification (SDS) written in Function Block Diagram (FBD), this method uses extended-structured decision tables (ESDTs). ESDTs include information related to the traceability analysis from a text-based SRS and a FBD-based SDS, respectively. Through comparing with both ESDTs from an SRS and ESDTs from an SDS, the effective traceability analysis of both a text-based SRS and a FBD-based SDS can be achieved. For the software design evaluation, a model checking, which is mainly used to verify PLC programs formally, is used in this research. A FBD-style design specification is translated into input languages of the SMV by translation rules and then the FBD-style design specification can be formally analyzed using SMV. (author)
Additional details
Publishing Information
- Publisher
- Atomic Energy Society of Japan
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- NUTHOS-6: Proceedings of the 6th international topical meeting on nuclear reactor thermal hydraulics, operations and safety
- Imprint Pagination
- 3690 p.
- Journal Page Range
- 18 p.
Conference
- Title
- 6. international topical meeting on nuclear reactor thermal hydraulics, operations and safety
- Acronym
- NUTHOS-6
- Dates
- 4-8 Oct 2004
- Place
- Nara (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 36093887
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ATWS; COMPUTER CODES; DESIGN; DIGITAL SYSTEMS; EVALUATION; MITIGATION; NUCLEAR POWER PLANTS; REACTOR CONTROL SYSTEMS; REACTOR INSTRUMENTATION; VERIFICATION
- Descriptors DEC
- ACCIDENTS; CONTROL SYSTEMS; DESIGN BASIS ACCIDENTS; NUCLEAR FACILITIES; POWER PLANTS; REACTOR ACCIDENTS; THERMAL POWER PLANTS
Optional Information
- Notes
- This CD-ROM can be used for WINDOWS 9x/NT/2000/ME/XP, MACINTOSH; Acrobat Reader is included; Data in PDF format, Folder Name THURSDAY October 7, 2004, Paper ID N6P171.pdf; 13 refs., 15 figs., 8 tabs.