Loss-of-coolant accident (LOCA) testing of aged cables for nuclear plant life extension
Sandia National Laboratories is conducting long-term aging research on representative samples of nuclear power plant Class 1E cables. The objectives of this program are to determine the suitability of these cables for extended life (beyond 40-year design basis) and to assess various cable condition monitoring (CM) techniques for predicting remaining cable life. Twelve different cable products have been aged for long times at relatively mild exposure conditions in three test chambers to nominal equivalent lifetimes of 20, 40, and 60 years. Following the aging process, the cables in each chamber were exposed to a sequential accident profile consisting of 110 Mrad of high dose rate gamma irradiation followed by a simulated design basis loss-of-coolant accident (LOCA) steam exposure (except the 20-year chamber, which has not yet been LOCA tested). This paper discusses the results of the LOCA testing on the cables aged to 60 years. Although some of the cables experienced electrical failures, the results of these tests indicate a good life extension potential for a number of popular cable products. 3 refs., 12 figs.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA)
- Sponsoring Organization:
- NRC
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 5432767
- Report Number(s):
- SAND-89-1755C; CONF-8910222--2; ON: DE90002103
- Country of Publication:
- United States
- Language:
- English
Similar Records
Condition monitoring and aging assessment of Class 1E cables
Cable condition monitoring research activities at Sandia National Laboratories
Long-term aging and loss-of-coolant accident (LOCA) testing of electrical cables
Conference
·
Thu Dec 31 23:00:00 EST 1987
·
OSTI ID:6828776
Cable condition monitoring research activities at Sandia National Laboratories
Conference
·
Thu Dec 31 23:00:00 EST 1987
·
OSTI ID:5431308
Long-term aging and loss-of-coolant accident (LOCA) testing of electrical cables
Technical Report
·
Tue Oct 01 00:00:00 EDT 1996
·
OSTI ID:385579
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
220900 -- Nuclear Reactor Technology-- Reactor Safety
36 MATERIALS SCIENCE
360603 -- Materials-- Properties
ACCIDENTS
AGING
CABLES
CONDUCTOR DEVICES
DATA ANALYSIS
ELECTRIC CABLES
ELECTRICAL EQUIPMENT
ELECTRICAL INSULATION
ELECTRICAL TRANSIENTS
EQUIPMENT
FAILURES
FORECASTING
LOSS OF COOLANT
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
RADIATION DOSE UNITS
RADIATION EFFECTS
REACTOR ACCIDENTS
REACTOR SAFETY
SAFETY
SERVICE LIFE
THERMAL POWER PLANTS
TRANSIENTS
UNITS
VOLTAGE DROP
220200* -- Nuclear Reactor Technology-- Components & Accessories
220900 -- Nuclear Reactor Technology-- Reactor Safety
36 MATERIALS SCIENCE
360603 -- Materials-- Properties
ACCIDENTS
AGING
CABLES
CONDUCTOR DEVICES
DATA ANALYSIS
ELECTRIC CABLES
ELECTRICAL EQUIPMENT
ELECTRICAL INSULATION
ELECTRICAL TRANSIENTS
EQUIPMENT
FAILURES
FORECASTING
LOSS OF COOLANT
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
RADIATION DOSE UNITS
RADIATION EFFECTS
REACTOR ACCIDENTS
REACTOR SAFETY
SAFETY
SERVICE LIFE
THERMAL POWER PLANTS
TRANSIENTS
UNITS
VOLTAGE DROP