A verification and validation method and its application to digital safety systems in ABWR nuclear power plants
- 1. Power and Ind. Syst. Res. and Dev. Center, Tokyo (Japan). Comput. Control Syst. Technol. Group
- 2. Toshiba Corp., Tokyo (Japan). Power Generation Control Syst. Dev. Dept.
- 3. Toshiba Corp., Yokohama (Japan). Nucl. Control and Electr. Eng. Dept.
- 4. Toshiba Corp., Tokyo (Japan). Technol. Planning Dept.
- 5. Nucl. Power Eng. Dept., Tokyo (Japan). Tokyo Electr. Power Co.
Description
A verification and validation (V and V) method has been developed and applied to newly developed digital safety systems for the first ABWR plant, Kashiwazaki-Kariwa unit No. 6 of the Tokyo Electric Power Company. This paper describes the method and experience gained from its application. The method was developed on the basis of domestic and foreign standards and guidelines, and covers the more concrete procedures required for actual V and V. The application of problem oriented language (POL) helps make the V and V feasible and reliable. A personal-computer-based automatic test tool for the validation test has been developed and utilized. This tool is used to carry out the pre-defined validation test procedure automatically and produce a test report, and it was found to be effective in reducing the time and manpower required for the validation test. The validation test covers dynamic transient tests in which the response of the digital safety system against the simulated design based transients are tested. The tool enables automatic execution of the dynamic test. (orig.)
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 183
- Journal Issue
- 1-2
- Journal Page Range
- p. 117-132
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Switzerland
- INIS RN
- 29049672
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- DESIGN BASIS ACCIDENTS; DIGITAL SYSTEMS; KASHIWAZAKI-KARIWA-6 REACTOR; LOGIC CIRCUITS; PROGRAMMING LANGUAGES; SAFETY ENGINEERING; SCRAM; VALIDATION; VERIFICATION
- Descriptors DEC
- ACCIDENTS; BWR TYPE REACTORS; ELECTRONIC CIRCUITS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR SHUTDOWN; REACTORS; SHUTDOWN; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 8 refs.