The Evaluation on Applying the Digital Safety System to Existing PWR Plants in Japan
Creators
- 1. The Kansai Electric Power Co., Inc. Nuclear Power Division 3-3-22, Nakanoshima Kita-ku, Osaka 530-8270 (Japan)
- 2. Mitsubishi Heavy Industries Ltd. Nuclear Energy Systems Engineering Center 1-1-1, Wadasaki Hyogo-ku, Kobe 652-8585 (Japan)
Description
To resolve the aging and obsolescence issues for instrumentation and control (I and C) systems at nuclear power plants, it is necessary to form a long-range maintenance and replacement plan for them systematically. To plan to replace the non-safety I and C system, the digital I and C system would be the most powerful choice from the view of maintainability and reliability because it has already been applied to our latest PWR plants. For the safety I and C system, even though digital safety system has already developed for the next PWR plants, it has never yet been applied to our plants. Therefore, how to apply digital safety systems to existing plants has been carefully studied. At first, the differences on safety functions, redundant architecture, and system interface between the next PWR plants and the existing plants have been studied. Then, the best replacement plan for safety I and C systems has been studied to obtain as much benefits as possible that are expected for the next plants, such as high reliability, availability, operability, maintainability and cost reduction. (authors)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the CNRA/CSNI workshop on licensing and operating experience of computer-based I and C systems
- Imprint Pagination
- 371 p.
- Journal Page Range
- p. 55-62
- Report number
- NEA-CSNI-R--2002-1
Conference
- Title
- CNRA/CSNI workshop on licensing and operating experience of computer-based I and C systems
- Dates
- 25-27 Sep 2001
- Place
- Hluboka nad Vltavou (Czech Republic)
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 39066660
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AGING; CONTROL; EVALUATION; MAINTENANCE; NUCLEAR POWER PLANTS; PWR TYPE REACTORS; REACTOR SAFETY; RELIABILITY
- Descriptors DEC
- ENRICHED URANIUM REACTORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTORS; SAFETY; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS