Effect of LOCA simulation procedures on cross-linked polyolefin cable's performance
Technical Report
·
OSTI ID:6834373
Electrical and mechanical properties of three commercial cross-linked polyolefin (XLPO) materials, typically used as electrical cable insulation, have been monitored during these simulations of nuclear power plant aging and accident stresses. For one XLPO cable accelerated thermal aging is performed, then the samples are irradiated to the combined aging and LOCA total dose. Finally, a steam exposure is applied. For a second and third set of XLPO cables simultaneous applications of elevated temperature and radiation stresses are used to preaccident age specimens. These aging exposures are followed by simultaneous and steam exposures to simulate a LOCA environment. The measurement parameters during these tests included: dc insulation resistance, ac leakage current, ultimate tensile strength, ultimate tensile elongation, percentage dimensional changes, and percentage moisture absorption. Test results for three XLPO materials are presented.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 6834373
- Report Number(s):
- NUREG/CR-3588; SAND-83-2406; ON: DE84013527
- Country of Publication:
- United States
- Language:
- English
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Aging, condition monitoring, and loss-of-coolant accident (LOCA) tests of Class 1E electrical cables. Volume 1, Crosslinked polyolefin cables
Aging, condition monitoring, and loss-of-coolant accident (LOCA) tests of Class 1E electrical cables: Summary of results
Technical Report
·
Sat Oct 01 00:00:00 EDT 1983
·
OSTI ID:5405566
Aging, condition monitoring, and loss-of-coolant accident (LOCA) tests of Class 1E electrical cables. Volume 1, Crosslinked polyolefin cables
Technical Report
·
Sat Aug 01 00:00:00 EDT 1992
·
OSTI ID:10177143
Aging, condition monitoring, and loss-of-coolant accident (LOCA) tests of Class 1E electrical cables: Summary of results
Conference
·
Sat Nov 30 23:00:00 EST 1991
·
OSTI ID:10102742
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210100 -- Power Reactors
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Light-Water Moderated
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Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
36 MATERIALS SCIENCE
360403 -- Materials-- Polymers & Plastics-- Mechanical Properties-- (-1987)
ACCIDENTS
AGING
BWR TYPE REACTORS
CABLES
CONDUCTOR DEVICES
ELECTRIC CABLES
ELECTRICAL EQUIPMENT
ELECTRICAL INSULATION
EQUIPMENT
LOSS OF COOLANT
MECHANICAL PROPERTIES
ORGANIC COMPOUNDS
ORGANIC POLYMERS
PHYSICAL RADIATION EFFECTS
POLYMERS
POLYOLEFINS
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
STRESSES
TENSILE PROPERTIES
THERMAL STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS