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          NRC Library  Document Collections  NUREG-Series Publications  Publications Prepared by NRC ContractorsEvaluation of Simulator Adequacy for the Radiation Qualification of Safety-Related Equipment (NUREG/CR-1184,SAND79-1787)

On this page: Publication Information AbstractDownload complete document NUREG/CR-1184 (PDF - 5.41 MB)Publication Information **Manuscript Completed:**August 1979**Date Published:**May 1980 **Prepared by:** Lloyd L. Bonzon and William H. Buckalew Sandia National Laboratories Albuquerque, NM 87185 Operated by Sandia Corporation for the U.S. Department of Energy **Prepared for:** Research Support Branch Office of Water Reactor Safety Research U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Under Interagency Agreement DOE 40-550-75 NRC FIN A-1051-0 Availability Notice Abstract This analysis of the response of a reactor power cable to a loss-of-coolant accident (LOCA) discusses several different possible failure mechanisms. In the first few fractions of a minute the electrical leakage currents flow and trapped electrons may discharge, inducing noise pulses into the cable. Quantitative analysis shows these effects are not serious for a power cable. If the cable has poor heat contact with the external environment, within a few minutes radiation energy (dose) will raise the temperature from an already elevated temperature to approach the maximum service temperature for the insulators. After a few days the accumulated dose is enough to deteriorate the cable insulation. This chemical and mechanical deterioration thus represents the ultimate failure mode of the cable. It is noted that gamma ray simulators may understress the electrical effects and overstress the temperature effects. It is also noted that several parameters used in this study were extrapolated from the values for roughly similar materials in roughly similar environments. A final, definitive study might have to include a program to measure these parameters in the materials of interest. 
      
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