Study on long-term irradiation aging of electrical cables (The VEILLE program)
- and others
The VEILLE program (French acronym for study on long-term irradiation aging of electrical cables) was implemented in 1988 by the Institute of Protection and Nuclear Safety (IPSN) in collaboration with the US Nuclear Regulatory Commission (NRC) for a period of six years. It is intended to validate the assumptions put forward as regards aging of electrical cables and to develop criteria for early detection of degradation likely to lead to functional failures. The tests were carried out partly at the Sandia National Laboratories in the United States, partly in France in the CIS bio international Laboratories at the Saclay Nuclear Research Centre. The study focused on the radiation effects from cobalt 60 on electrical cables made up of various polymers for two temperatures and at various dose rates. Other tests were also performed using a device laid under water in the OSIRIS reactor pool at Saclay to test cables under irradiation and temperature conditions close to those found in nuclear power plant operation. Subsequently the aged cables were subjected to containment accident conditions (irradiation and thermodynamic profile) in order to show any degradation due to aging. The study showed the significant effect of radiation doses on EPR and EPDM cable insulations as well as synergy between radiation dose rates and temperature on the mechanical properties of the Hypalon sheath. Correlation between the mechanical properties and the function of cables is difficult to establish as electrical characteristics are preserved whatever the type of mechanical degradation observed. Finally, the performance of electrical cables after an accident remains a key criterion to define the materials likely to be used when manufacturing cables intended to ensure safety functions.
- Research Organization:
- US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Office of Nuclear Regulatory Research; Brookhaven National Lab. (BNL), Upton, NY (United States)
- OSTI ID:
- 93880
- Report Number(s):
- NUREG/CP-0140-Vol.3; ON: TI95011768; TRN: 95:005142-0009
- Resource Relation:
- Other Information: PBD: Apr 1995; Related Information: Is Part Of Twenty-second water reactor safety information meeting: Proceedings. Volume 3: Primary systems integrity; Structural and seismic engineering; Aging research, products and applications; Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)]; PB: 269 p.
- Country of Publication:
- United States
- Language:
- English
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