Aging, condition monitoring, and loss-of-coolant accident (LOCA) tests of Class 1E electrical cables: Summary of results
Abstract
This paper summarizes the results of aging, condition monitoring, and accident testing of Class 1E cables used in nuclear power generating stations. Three sets of cables were aged for up to 9 months under simultaneous thermal ({approx equal} 100{degrees}C) and radiation ({approx equal}0.10 kGy/hr) conditions. After the aging, the cables were exposed to a simulated accident consisting of high dose rate irradiation ({approx equal}6 kGy/hr) followed by a high temperature steam exposure. A fourth set of cables, which were unaged, were also exposed to the accident conditions. The cables that were aged for 3 months and then accident tested were subsequently exposed to a high temperature steam fragility test (up to 400{degrees}C), while the cables that were aged for 6 months and then accident tested were subsequently exposed to a 1000-hour submergence test in a chemical solution. The results of the tests indicate that the feasibility of life extension of many popular nuclear power plant cable products is promising and that mechanical measurements (primarily elongation, modulus, and density) were more effective than electrical measurements for monitoring age-related degradation. In the high temperature steam test, ethylene propylene rubber (EPR) cable materials generally survived to higher temperatures than crosslinked polyolefin (XLPO) cablemore »
- Authors:
- Publication Date:
- Research Org.:
- Sandia National Labs., Albuquerque, NM (United States)
- Sponsoring Org.:
- USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
- OSTI Identifier:
- 6075570
- Report Number(s):
- SAND-91-1397C; CONF-911079-12
ON: DE92003615
- DOE Contract Number:
- AC04-76DP00789
- Resource Type:
- Conference
- Resource Relation:
- Conference: 19. Nuclear Regulatory Commission (NRC) water reactor safety information meeting, Bethesda, MD (United States), 28-30 Oct 1991
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 22 GENERAL STUDIES OF NUCLEAR REACTORS; ELECTRIC CABLES; AGING; RADIATION EFFECTS; THERMAL DEGRADATION; NUCLEAR POWER PLANTS; LOSS OF COOLANT; RADIATION DOSES; REACTOR SAFETY; THERMAL CYCLING; ACCIDENTS; CABLES; CONDUCTOR DEVICES; DOSES; ELECTRICAL EQUIPMENT; EQUIPMENT; NUCLEAR FACILITIES; POWER PLANTS; REACTOR ACCIDENTS; SAFETY; THERMAL POWER PLANTS; 220900* - Nuclear Reactor Technology- Reactor Safety; 220200 - Nuclear Reactor Technology- Components & Accessories
Citation Formats
Jacobus, M J. Aging, condition monitoring, and loss-of-coolant accident (LOCA) tests of Class 1E electrical cables: Summary of results. United States: N. p., 1991.
Web.
Jacobus, M J. Aging, condition monitoring, and loss-of-coolant accident (LOCA) tests of Class 1E electrical cables: Summary of results. United States.
Jacobus, M J. 1991.
"Aging, condition monitoring, and loss-of-coolant accident (LOCA) tests of Class 1E electrical cables: Summary of results". United States.
@article{osti_6075570,
title = {Aging, condition monitoring, and loss-of-coolant accident (LOCA) tests of Class 1E electrical cables: Summary of results},
author = {Jacobus, M J},
abstractNote = {This paper summarizes the results of aging, condition monitoring, and accident testing of Class 1E cables used in nuclear power generating stations. Three sets of cables were aged for up to 9 months under simultaneous thermal ({approx equal} 100{degrees}C) and radiation ({approx equal}0.10 kGy/hr) conditions. After the aging, the cables were exposed to a simulated accident consisting of high dose rate irradiation ({approx equal}6 kGy/hr) followed by a high temperature steam exposure. A fourth set of cables, which were unaged, were also exposed to the accident conditions. The cables that were aged for 3 months and then accident tested were subsequently exposed to a high temperature steam fragility test (up to 400{degrees}C), while the cables that were aged for 6 months and then accident tested were subsequently exposed to a 1000-hour submergence test in a chemical solution. The results of the tests indicate that the feasibility of life extension of many popular nuclear power plant cable products is promising and that mechanical measurements (primarily elongation, modulus, and density) were more effective than electrical measurements for monitoring age-related degradation. In the high temperature steam test, ethylene propylene rubber (EPR) cable materials generally survived to higher temperatures than crosslinked polyolefin (XLPO) cable materials. In dielectric testing after the submergence testing, the XLPO materials performed better than the EPR materials. This paper presents some recent experimental data that are not yet available elsewhere and a summary of findings from the entire experimental program.},
doi = {},
url = {https://www.osti.gov/biblio/6075570},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Jan 01 00:00:00 EST 1991},
month = {Tue Jan 01 00:00:00 EST 1991}
}