Three Mile Island techniques to detect degradation in electrical measurement and control circuits
Creators
- 1. Idaho National Engineering Lab., EG and G Idaho, Inc., Idaho Falls, ID
Description
This paper discusses electrical techniques that have been used by EG and G, Idaho Inc. to assess the condition of the electrical systems at Three Mile Island Unit 2 (TMI-2) subsequent to the accident of March 28, 1979. These same techniques could be used to monitor aging at any similar facility. The direct current and radio-frequency electrical testing techniques have been used to determine the qualitative condition of electrical systems within the TMI-2 Reactor Building. Typical circuits of the electrical systems are defined and both theoretical and actual data are presented. Fundamental analysis techniques and their application to understanding plant aging and improved safety is discussed. The electrical systems all treated as circuits include all interconnections and cabling
Additional details
Publishing Information
- Publisher
- American Society of Metals.
- Imprint Place
- Metals Park, OH (USA)
- Imprint Title
- Proceedings of the international conference on nuclear power plant aging, availability factor and reliability analysis
- Journal Page Range
- p. 35-42.
Conference
- Title
- International conference on nuclear power plant aging, availability factor and reliability analysis.
- Dates
- 7-12 Jul 1985.
- Place
- San Diego, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17073860
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AGING; DIRECT CURRENT; ELECTRIC CABLES; ELECTRICAL TESTING; ELECTRONIC CIRCUITS; LOSS OF COOLANT; MONITORING; PHYSICAL RADIATION EFFECTS; POST-IRRADIATION EXAMINATION; REACTOR COMPONENTS; REACTOR SAFETY; RF SYSTEMS; THREE MILE ISLAND-2 REACTOR
- Descriptors DEC
- ACCIDENTS; CABLES; CONDUCTOR DEVICES; CURRENTS; ELECTRIC CURRENTS; ELECTRICAL EQUIPMENT; ENRICHED URANIUM REACTORS; EQUIPMENT; MATERIALS TESTING; NONDESTRUCTIVE TESTING; POWER REACTORS; PWR TYPE REACTORS; RADIATION EFFECTS; REACTOR ACCIDENTS; REACTORS; SAFETY; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS