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U.S. Department of Energy
Office of Scientific and Technical Information

Application of noise analysis to safety-related assessments and reactor diagnostics

Conference ·
OSTI ID:5379158
Noise analysis methods were used to assess anomalous in-core temperature fluctuations at the Fort St. Vrain gas-cooled reactor and postaccident reactor conditions at Three Mile Island, Unit 2. In addition to these applications of noise analysis, the underlying technology is developed concerning (1) analytical methods for predicting noise signatures under postulated anomalous conditions, (2) techniques for on-line monitoring of boiling water reactor stability, (3) new methods for locating and characterizing loose or drifting metallic objects in reactor coolant systems, and (4) acquisition of baseline noise signatures for commercial pressurized water reactors.
Research Organization:
Oak Ridge National Lab., TN (USA)
DOE Contract Number:
W-7405-ENG-26
OSTI ID:
5379158
Report Number(s):
CONF-800403-30
Country of Publication:
United States
Language:
English