학술논문

Condition assessment of cable insulation systems in operating nuclear power plants
Document Type
Periodical
Source
IEEE Transactions on Dielectrics and Electrical Insulation IEEE Trans. Dielect. Electr. Insul. Dielectrics and Electrical Insulation, IEEE Transactions on. 6(3):376-384 Jun, 1999
Subject
Fields, Waves and Electromagnetics
Engineered Materials, Dielectrics and Plasmas
Cable insulation
Testing
Accidents
Paramagnetic resonance
Wounds
Aging
Polyethylene
Rubber
Cables
Acceleration
Language
ISSN
1070-9878
1558-4135
Abstract
Four crosslinked polyethylene (XLPE) and ethylene propylene rubber (EPR) insulated cables were subjected to accelerated thermal, radiation, and sequential radiation and thermal exposure to simulate 20, 30, and 40 yr in-service environments in Ontario Hydro Nuclear Plants. Two sets of samples were evaluated. The first set contained 15 cm cable specimens in tubular form with the conductors removed, while the second set was made up of 4.3 m cable samples wound on mandrels. The cable samples were sequentially irradiated and thermally aged and subjected to an additional accident radiation exposure followed by a simulated loss of coolant accident (LOCA)/main steam line break (MSLB) steam test. During the steam test, samples were energized and their electrical characteristics continuously monitored. The material performance of the insulation was assessed using the 15 cm specimens during the various stages of aging exposure by conventional elongation measurement and by the use of micro-specimens with differential scanning calorimeter (DSC), oxidation induction time (OIT) and infrared carbonyl absorption techniques. The results from these samples were compared with the electrical performance of the cable samples wound on mandrels that had been subjected to the LOCA/MSLB steam test. The test results indicate that with the use of micro-specimens meaningful changes were obtained until the elongation values of the samples were reduced to 50% absolute. Electrical test data obtained for XLPE and EPR during the steam tests indicate that 50% absolute elongation values provide sufficient margin to withstand additional accident radiation, and to function electrically during design basis events.