Recent results of an experimental study on the impact of smoke on digital I and C equipment [electronic resource].
- Rockville, Md. : U.S. Nuclear Regulatory Commission, 1998.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Physical Description:
- pages 163-180 : digital, PDF file
- Additional Creators:
- U.S. Nuclear Regulatory Commission
United States. Department of Energy. Office of Scientific and Technical Information
- A program to assess the impact of smoke on digital instrumentation and control (I and C) safety systems began in 1994, funded by the US Nuclear Regulatory Commission Office of Research. Digital I and C safety systems are likely replacements for today`s analog systems. The nuclear industry has little experience in qualifying digital electronics for critical systems, part of which is understanding system performance during plant fires. The results of tests evaluating the performance of digital circuits and chip technologies exposed to the various smoke and humidity conditions representative of cable fires are discussed. Tests results show that low to moderate smoke densities can cause intermittent failures of digital systems. Smoke increases leakage currents between biased contacts, leading to shorts. Chips with faster switching times, and thus higher output drive currents, are less sensitive to leakage currents and thus to smoke. Contact corrosion from acidic gases in smoke and inductance of stray capacitance are less important contributors to system upset. Transmission line coupling was increased because the smoke acted as a conductive layer between the lines. Permanent circuit damage was not obvious in the 24 hr of circuit monitoring. Test results also show that polyurethane, parylene, and acrylic conformal coatings are more effective in protecting against smoke than epoxy or silicone. Common-sense mitigation measures are discussed. Unfortunately the authors are a long way from standard tests for smoke exposure that capture the variations in smoke exposure possible in an actual fire.
- Published through SciTech Connect.
25. water reactor safety information meeting, Bethesda, MD (United States), 20-22 Oct 1997.
Tanaka, T.J.; Antonescu, C.
- Funding Information:
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