Probabilistic Techniques for Diagnosis of Multiple Component Degradations

References

• T. H. BOND, “Performance Monitoring and Predictive Maintenance,” Nucl. Plant J., 6, 93 (1988).
   Google Scholar
• J. REIFMAN and J. C. LEE, “Reactor Diagnostics Rule Generation Through Statistical Pattern Recognition,” Nucl. Sci. Eng., 107, 291 (1991).
   Web of Science ®Google Scholar
• T. J. LAFFEY, T. J. COX, J. L. SCHMIDT, S. M. KAO, and J. READ, “Real-Time Knowledge-Based Systems,” AI Magazine (Spring 1988).
   Google Scholar
• P. J. RANK and J. C. LEE, “Fuzzy Logic Approach for Transient Diagnostics in Nuclear Power Plants,” Trans. Am. Nucl. Soc., 70, 104 (1994).
   Google Scholar
• A. G. PARLOS, J. MUTHUSAMI, and A. F. ATIYA, “Incipient Fault Detection and Identification in Process Systems Using Accelerated Neural Network Learning,” Nucl. Technol., 105, 145 (1994).
   Web of Science ®Google Scholar
• J. A. HASSBERGER and J. C. LEE, “A Simulation-Based Expert System for Nuclear Power Plant Diagnostics,” Nucl. Sci. Eng., 102, 153 (1989).
   Web of Science ®Google Scholar
• P. M. FRANK, “Fault Diagnosis in Dynamic Systems Using Analytical and Knowledge Based Redundancy—A Survey and New Results,” Automatica, 26, 459 (1990).
   Web of Science ®Google Scholar
• J. J. GERTLER, Fault Detection and Diagnosis in Engineering Systems, Marcel Dekker (1998).
   Google Scholar
• H. HAMMOURI, P. KABORE, and M. KINNAERT, “A Geometric Approach to Fault Detection and Isolation for Bilinear Systems,” IEEE Trans. Automat. Contr., 46, 1451 (2001).
   Web of Science ®Google Scholar
• C. D. PERSIS, and A. ISIDORI, “A Geometric Approach to Nonlinear Fault Detection and Isolation,” IEEE Trans. Automat. Contr., 46, 853 (2001).
   Web of Science ®Google Scholar
• C. GUERNEZ, J. P. CASSAR, and M. STAROSWIECKI, “Extension of Parity Space to Nonlinear Polynomial Dynamic Systems,” Proc. Symp. Fault Detection, Supervision, and Safety of Technical Processes (Safeprocess’97), Hull, United Kingdom, August 26–28, 1997, International Federation of Automatic Control (1997).
   Google Scholar
• Q. ZHANG, M. BASSEVILLE, and A. BENVENISTE, “Fault Detection and Isolation in Nonlinear Dynamic Systems: A Combined Input-Output and Local Approach,” Automatica, 34, 1359 (1998).
   Web of Science ®Google Scholar
• M. FLIESS and C. JOIN, “An Algebraic Approach to Fault Diagnosis for Linear Systems,” Proc. Multiconference Computational Engineering in Systems Applications (CESA 2003), Lille, France, July 9–11, 2003, International Association for Mathematics and Computers in Simulation (2003).
   Google Scholar
• A. RACZ, “Detection of Small Leakages by a Combination of Dedicated Kalman Filters and an Extended Version of the Binary Sequential Probability Ratio Test,” Nucl. Technol., 104, 128 (1993).
   Web of Science ®Google Scholar
• K. C. GROSS and K. E. HUMENICK, “Sequential Probability Ratio Test for Nuclear Plant Component Surveillance,” Nucl. Technol., 9, 131 (1991).
   Google Scholar
• H. U. VOSS, J. TIMMER, and J. KURTHS, “Nonlinear Dynamical System Identification from Uncertain and Indirect Measurements,” Int. J. Bifurcation Chaos, 14, 1905 (2004).
   Web of Science ®Google Scholar
• P. WANG and T. ALDEMIR, “Some Improvements in State/Parameter Estimation Using the Cell-to-Cell Mapping Technique,” Nucl. Sci. Eng., 147, 1 (2004).
   Google Scholar
• I. MUNTEANU and T. ALDEMIR, “On-Line Risk Monitoring of Dynamic Systems,” Proc. Int. Topl. Mtg. Probabilistic Safety Assessment, Detroit, Michigan, October 6–9, 2002, p. 622, American Nuclear Society (2002) (CD-ROM).
   Google Scholar
• “An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis,” Regulatory Guide 1.174, U. S. Nuclear Regulatory Commission (2002).
   Google Scholar
• K. N. FLEMING “Markov Models for Evaluating Risk-Informed In-Service Inspection Strategies for Nuclear Power Plant Piping Systems,” Reliab. Eng. Syst. Safety, 83, 27 (2004).
   Google Scholar
• “Component Reliability Database,” IAEA-TECDOC-478, International Atomic Energy Agency (1988).
   Google Scholar
• “IEEE Guide to the Collection and Presentation of Electrical, Electronic, Sensing Component, and Mechanical Equipment Reliability Data for Nuclear-Power Generating Stations,” IEEE Std. 500, IEEE Power Engineering Society (1984).
   Google Scholar
• T. ALDEMIR, “Some Measure-Thoretic Issues in the Implementation of Dynamic Methodologies for PRA,” Trans. Am. Nucl. Soc., 89, 410 (2003).
   Google Scholar
• C. W. GARDINER, Handbook of Stochastic Methods, Springer-Verlag (1985).
   Google Scholar
• A. Z. AKCASU and B. HAMMOUDA, “Motion of a Charged Particle in a Randomly Varying Magnetic Field,” Physica, 131A, 485 (1985).
   Google Scholar
• J. DEVOOGHT and C. SMIDTS, “Probabilistic Reactor Dynamics—I: Theory of Continuous Event Trees,” Nucl. Sci. Eng., 111, 229 (1992).
   Web of Science ®Google Scholar
• S. E. AUMEIER, “Probabilistic Techniques for System Diagnostics and Surveillance,” PhD Dissertation, Department of Nuclear Engineering, University of Michigan (1994).
   Google Scholar
• C. SMIDTS and J. DEVOOGHT, “Probabilistic Reactor Dynamics—II: A Monte Carlo Study of a Fast Reactor Transient,” Nucl. Sci. Eng., 111, 241 (1992).
   Web of Science ®Google Scholar
• S. E. AUMEIER and J. C. LEE, “A Monte Carlo Technique for System Diagnostics, Monitoring, and Surveillance,” Trans. Am. Nucl. Soc., 69, 235 (1993).
   Google Scholar
• A. H. JAZWINSKI, Stochastic Processes and Filtering Theory, Academic Press (1970).
   Google Scholar
• M. R. SPIEGLE, Shaum’s Outline of Theory and Problems of Probability and Statistics, McGraw Hill (1992).
   Google Scholar
• R. F. STENGEL, Optimal Control and Estimation, Dover Publications (1994).
   Google Scholar
• N. J. McCORMICK, Reliability and Risk Analysis, Academic Press (1981).
   Google Scholar
• “Reactor Safety Study,” NUREG-75/014 (WASH-1400), U.S. Nuclear Regulatory Commission (1975).
   Google Scholar
• R. L. IMAN and M. J. SHORTENCARIER, “AFortran-77 Program and User’s Guide for the Generation of Latin Hypercube and Random Samples for Use with Computer Models,” NUREG-CR-3624, U.S. Nuclear Regulatory Commission (1984).
   Google Scholar
• J. A. HODDE, “Control Rod Oscillation and Transient Pressure Tests—Big Rock Point Boiling Water Reactor,” GEAP-4448, General Electric Company (1966).
   Google Scholar
• J. A. HODDE, “Core Performance and Transient Flow Testing—Big Rock Point Boiling Water Reactor,” GEAP-4496, General Electric Company (1965).
   Google Scholar
• W. J. KEARTON, Steam Turbine Theory and Practice, Pitman and Sons (1961).
   Google Scholar
• P. V. G. SHANKAR, “Simulation Model of a Nuclear Reactor Turbine,” Nucl. Eng. Des., 44, 269 (1977).
   Google Scholar
• D. R. TOLAR and E. W. LARSEN, “A Transport Condensed History Algorithm for Electron Monte Carlo Simulations,” Nucl. Sci. Eng., 139, 47 (2001).
   Web of Science ®Google Scholar