Published April 1992 | Version v1
Report Metadata-only

New method for detecting degradation in installed cables in nuclear power plants

Creators

  • 1. Japan Atomic Energy Research Inst., Takasaki (Japan)

Description

The object of the investigation is to develop nondestructive detecting method for degradation of cables installed in nuclear power plants from the viewpoint of the safety operation and the life extension of the plants. Two kinds of detecting method (a) torque-strain response and (b) thermogravimetry were studied in order to apply to the low voltage cables, for which effective detecting methods have not been completed. Applicability of the methods to the low voltage CV cables (cross-linked polyethylene insulation, polyvinylchloride jacket) were discussed by using elongation at break as a primary standard

Additional details

Publishing Information

Imprint Title
Proceedings of the US Nuclear Regulatory Commission nineteenth water reactor safety information meeting. Volume 1, Plenary session; Pressure vessel and piping integrity; Metallurgy and NDE; Aging and components; Probabilistic risk assessment topics
Imprint Pagination
523 p.
Journal Page Range
p. 261-273.
Report number
NUREG/CP--0119-Vol.1

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
24027102
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; FIRE RESISTANCE; IRRADIATION; NONDESTRUCTIVE TESTING; PERFORMANCE; PHYSICAL RADIATION EFFECTS; POWER SYSTEMS; PWR TYPE REACTORS; REACTOR OPERATION; REACTOR SAFETY; SERVICE LIFE; STRAINS; THERMAL GRAVIMETRIC ANALYSIS; THERMAL STRESSES; TORQUE
Descriptors DEC
CABLES; CHEMICAL ANALYSIS; CONDUCTOR DEVICES; DEFORMATION; ELECTRICAL EQUIPMENT; ENRICHED URANIUM REACTORS; EQUIPMENT; GRAVIMETRIC ANALYSIS; LIFETIME; MATERIALS TESTING; OPERATION; POWER REACTORS; QUANTITATIVE CHEMICAL ANALYSIS; RADIATION EFFECTS; REACTORS; SAFETY; STRESSES; TESTING; THERMAL ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-911079--Vol.1.