Methods and tools used at the IPSN for the safety assessment of critical software
Creators
- 1. Institut de Protection et de Surete Nucleaire, Fontenay aux Roses (France)
Description
A significant feature of EDF's latest 1400MWe ''N4'' generation of pressurized water reactor (PWR) is the extensive use of computerized instrumentation and control, including a fully digital system for the reactor protection function. For the safety assessment of the software driving the operation of this digital reactor protection called SPIN, IPSN has developed and implemented a set of methods and tools. Using the lessons learned from this experience, IPSN has worked at improving those methods and tools, mainly trying to make them more automatic to use, and has participated in an international assessment exercise to test some other methods and tools, either new products on the market or self-developed products. As a result of these works, this paper presents an up to date overview of the IPSN methods and tools used for the assessment of safety critical software. This assessment, which consists of an analysis of all the documentation associated with the technical specifications and of a representative set of functions, is usually carried out in five steps: (1) critical examination of the documents, (2) evaluation of the quality of the code, (3) determination of the critical software components, (4) development of test cases and choice of testing strategy, (5) dynamic analysis (consistency and robustness). This paper also presents methods and tools developed or implemented by IPSN in order to: evaluate the completeness and consistency of specification and design documents written in natural language; build a model and simulate specification or design items; evaluate the quality of the source code; carry out FMEA analysis; run the binary code and perform tests (CLAIRE); perform random or mutational tests. (author)
Files
30017048.pdf
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Additional details
Publishing Information
- Imprint Title
- Specialists meeting on design and assessment of instrumentation and control systems in NPP coping with rapid technological change
- Imprint Pagination
- 188 p.
- Journal Page Range
- p. 33-41
- Report number
- IAEA-IWG-NPPCI--98/3
Conference
- Title
- Specialists meeting on design and assessment of instrumentation and control systems in NPP coping with rapid technological change
- Dates
- 6-8 Oct 1998
- Place
- Garching (Germany)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 30017048
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED CONTROL SYSTEMS; DIGITAL SYSTEMS; INTERNATIONAL COOPERATION; NUCLEAR POWER PLANTS; PWR TYPE REACTORS; QUALITY CONTROL; REACTOR INSTRUMENTATION; REACTOR SAFETY; SAFETY ANALYSIS; VALIDATION
- Descriptors DEC
- CONTROL; CONTROL SYSTEMS; COOPERATION; ENRICHED URANIUM REACTORS; NUCLEAR FACILITIES; ON-LINE CONTROL SYSTEMS; ON-LINE SYSTEMS; POWER PLANTS; POWER REACTORS; REACTORS; SAFETY; TESTING; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 4 refs