New method for detecting degradation in installed cables in nuclear power plants
- 1. Japan Atomic Energy Research Inst., Tokyo (Japan)
- 2. Hitachi Cable, Tokyo (Japan)
Description
Simple and precise methods for detecting degradation in installed cables in nuclear power plants are expected to develop from the viewpoint of the safety operation and the life extension of the plants. Generally, the degradation of cable insulation by thermal and/or radiation aging has been examined by tensile tests, and the degree of degradation was evaluated from the ultimate strength and elongation. The degradation of cables installed in the facility is likely to be detected by non-destructive techniques. For this purpose, two kinds of detecting methods i.e., (a) torque-strain response and (b) thermal gravimetry were studied in order to apply to the low voltage cables, for which effective detecting methods have not been completed. The paper describes a basic idea to determine degradation of the low voltage CV-cables (polyethylene insulation, polyvinylchloride jacket). Elongation at break was used as a primary standard to evaluate availability of the methods
Files
Additional details
Publishing Information
- Imprint Title
- Transactions of the nineteenth water reactor safety information meeting
- Imprint Pagination
- 220 p.
- Journal Page Range
- p. 7.5-7.6.
- Report number
- NUREG/CP--0118
Conference
- Title
- 19. Nuclear Regulatory Commission (NRC) water reactor safety information meeting.
- Dates
- 28-30 Oct 1991.
- Place
- Bethesda, MD (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23059447
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCURACY; AGING; AVAILABILITY; BWR TYPE REACTORS; ELECTRIC CABLES; ELONGATION; NONDESTRUCTIVE TESTING; PERFORMANCE; PHYSICAL RADIATION EFFECTS; POWER SYSTEMS; PWR TYPE REACTORS; REACTOR OPERATION; REACTOR SAFETY; SERVICE LIFE; STRAINS; THERMAL STRESSES; TORQUE
- Descriptors DEC
- CABLES; CONDUCTOR DEVICES; DEFORMATION; ELECTRICAL EQUIPMENT; ENRICHED URANIUM REACTORS; EQUIPMENT; LIFETIME; MATERIALS TESTING; OPERATION; POWER REACTORS; RADIATION EFFECTS; REACTORS; SAFETY; STRESSES; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-911079--.