A recently developed technique “Spread Spectrum Time Domain Reflectometry” (SSTDR), and supporting test devices will be adapted and tested to monitor and diagnose nuclear plant electrical systems. Current time domain reflectometry methods cannot detect or locate small faults after arc fault events, because their impedance discontinuity is too small and transient to create a measurable reflection. However, on-line, unobtrusive SSTDR can detect and locate arc and other electrical faults when the (∼msec) short circuit returns a strong reflected signal. These observations have led to development of SSTDR. If SSTDR can be successfully adapted to present and future nuclear plant electrical systems, it will be possible to monitor, on-line, the integrity of the electrical system continuously and with only minor equipment modification and no consequential safety issues. An integrated circuit (IC) is under development at the University of Utah for applications in the aircraft industry that will be adapted and used for this proposed development.
Skip Nav Destination
18th International Conference on Nuclear Engineering
May 17–21, 2010
Xi’an, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4929-3
PROCEEDINGS PAPER
Spread Spectrum Time Domain Reflectrometry Applied to Electrical Systems in Nuclear Power Plants
Gary M. Sandquist,
Gary M. Sandquist
Applied Science Professionals, LLC, Salt Lake City, UT
Search for other works by this author on:
Carl J. Sandquist
Carl J. Sandquist
Applied Science Professionals, LLC, Salt Lake City, UT
Search for other works by this author on:
Gary M. Sandquist
Applied Science Professionals, LLC, Salt Lake City, UT
Carl J. Sandquist
Applied Science Professionals, LLC, Salt Lake City, UT
Paper No:
ICONE18-29324, pp. 109-111; 3 pages
Published Online:
April 8, 2011
Citation
Sandquist, GM, & Sandquist, CJ. "Spread Spectrum Time Domain Reflectrometry Applied to Electrical Systems in Nuclear Power Plants." Proceedings of the 18th International Conference on Nuclear Engineering. 18th International Conference on Nuclear Engineering: Volume 1. Xi’an, China. May 17–21, 2010. pp. 109-111. ASME. https://doi.org/10.1115/ICONE18-29324
Download citation file:
12
Views
Related Proceedings Papers
Related Articles
High Temperature Silicon Integrated Circuits and Passive Components for Commercial and Military Applications
J. Eng. Gas Turbines Power (October,1999)
Multi-Level Hypotheses Testing for Fault Detection in Continuous Process
J. Dyn. Sys., Meas., Control (December,1990)
Sequential Testing for Fault Detection in Multiply-Redundant Systems
J. Dyn. Sys., Meas., Control (June,1989)
Related Chapters
Introduction
Fundamentals of Nuclear Fuel
Test and Diagnosis Model of Complicated Integrated Circuit with CPU
International Conference on Information Technology and Management Engineering (ITME 2011)
Introduction
Nuclear Reactor Thermal-Hydraulics: Past, Present and Future