Title of article :
Current research results on the technical basis for environmental qualification of safety-related digital 1&C hardware in nuclear power plants
Author/Authors :
Tanaka، T. نويسنده , , Korsah، K. نويسنده , , Ewing، P.D. نويسنده , , Kercel، S. نويسنده , , Wood، R.T. نويسنده , , Antonescu، C. نويسنده ,
Issue Information :
دوهفته نامه با شماره پیاپی سال 1999
Pages :
-250
From page :
251
To page :
0
Abstract :
This paper presents progress lo date of an NRC-sponsored conlirmatory research program iniliated to address hardware issues associated with the use of safely-related digital instrumentation and control (1&C) hardware in nuclear power plants. In particular, the potential vulnerability of digital technology to environmental stress effects and means for establishing environmental compatibility for digital 1&C systems were studied. The research approach involved evaluating existing military and industrial guidance, identifying the most significant environmental stressors and. for advanced 1&C systems in nuclear power plants, investigating the likely failure modes- both at the integrated circuit and system level-for digital technologies under varying levels of environmental stress. Environmental stressors used in the studies included smoke exposure, electromagnetic and radio-frequency interference (EMI/RFI), temperature, and humidity. The insights gained from these studies are being used to recommend appropriate methods for qualifying safety-related digital equipment in nuclear power plants. To characterize the EMI/RFI environment at current LWRs and to estimate the expected environment at ALWRs, ORNL conducted a long-term survey of ambient electromagnetic conditions at several nuclear power plants. A representative sampling of power plant conditions (reactor type, operating mode, site location) were monitored over extended observation periods (e.g., continuous measurements for up to 5 weeks at a single location) were selected to more completely determine the characteristic electromagnetic environment for nuclear power plants. The results of this study contributed to the technical basis for a Nuclear Regulatory Commission Draft Regulatory Guide (DG-1029) issued for comment in 1998. © 1999 Published by Elsevier Science S.A. All rights reserved.
Keywords :
Transient data collection , Fatigue monitoring , Pressurized water reactors
Journal title :
Nuclear Engineering and Design
Serial Year :
1999
Journal title :
Nuclear Engineering and Design
Record number :
14344
Link To Document :
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