Critical States of Nuclear Power Plant Reactors and Bilinear Modeling
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We present a new system methodology for modeling of nonlinear processes in nuclear power plant cores. This methodology makes use of a variety of different approaches from different mathematical fields. The problem of modeling critical states is reduced to a bilinear subproblem. A scheme which provides stable parameter identification and adaptive control for the nuclear nuclear power plant described by the bilinear differential equation is presented. Abnormal events are found via a system-theoretical approach. Transitions to critical states can be detected by bilinear analysis of observed characteristics and by optimization of sensory measurements. Latent conditions and critical parameters in the reactor core are estimated trough a bilinear modeling.
KeywordsNuclear Power Plant International Atomic Energy Agency Universal Model Reactor Core Nonlinear Control System
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- 1.V. Arnold. Singularities of smooth mappings. Uspekhi Mat. Nauk., 23(1):3–44, 1968.Google Scholar
- 2.D. Bell and S. Glesston. Theory of nuclear reactors. Moscow, Atomizdat, 1974.Google Scholar
- 5.K. Chitkara and J. Weisman. Equilibrium approach to optimal in-core fuel management for pressurized water reactors. Nucl. Technol., 24(1):33–49, 1974.Google Scholar
- 9.R. R. Fullwood and R. E. Hall. Probabilistic risk assessment in the nuclear power industry: fundamentals and applications. Butterworth-Heinemann, New York, 1988.Google Scholar
- 10.V. Goldin, G. Pestriakova, Y. Troishchev, and E. Aristova. Neutron and nuclear regime with self-organisation in reactor with the hard spectrum and carbide fuel. Math. Model., 14(1):27–39, 2002.Google Scholar
- 11.C. S. Gordelier. Nuclear energy risks and benefits in perspective. NEA News, 25(2):4–8, 2007.Google Scholar
- 12.Greenpeace. Subject: Calender of Nuclear Accidents and Events (Updated 21st March), 2007. http://archieve.greenpeace.org/comms/nukes/chernob/rep02.html.
- 13.L. Hunt, R. Su, and G. Meyer. Global transformations of nonlinear systems. IEEE Trans. Autom. Contr., 25(2):4–8, 2007.Google Scholar
- 14.International Atomic Energy Agency. Accident analysis for RBMKs. Safety Reports Series No. 43, IAEA, Vienna, 2005.Google Scholar
- 15.International Atomic Energy Agency. Annual Report 2006. IEA, Vienna, 2006.Google Scholar
- 16.International Energy Agency. IEA energy technology essentials: Nuclear power. IEA, Vienna, March 2007.Google Scholar
- 20.Zhian Li, P. M. Pardalos, and S. H. Levine. Space-covering approach and modified Frank-Wolfe algorithm for optimal nuclear reactor reload design. Recent advances in global optimization. Princeton University Press, New Jersey, 1992.Google Scholar
- 21.G. Marchuk. Methods of nuclear reactors calculations. Samizdat, Moscow, 1961.Google Scholar
- 22.N. J. McCormick. Reliability and risk analysis: methods and nuclear power applications. Academic, New York, 1981.Google Scholar
- 24.A. Veinberg and E. Vigner. Physical theory of nuclear reactors [Russian translation]. IL, Moscow, 1961.Google Scholar
- 25.M. L. Wald. Approval is sought for reactors. The New York Times, pages C1–C11, September 25, 2007.Google Scholar
- 26.V. Yatsenko. An engineering design method for automatic control of transverse magnetic field in tokamaks. Proceedings of Conference on The 2nd All-Union Conference on the Engineering Problems of Thermonuclear Reactors, pages 272–273, 1981.Google Scholar
- 28.V. Yatsenko. Methods of risk analysis for energy objects. Proceedings of Conference on International Energy Conference, July 23–28, Las Vegas, Nevada, USA pages 272–273, 2000.Google Scholar
- 29.V. Yatsenko. Reliability forecasting of nuclear reactor in fuzzy environment. Proceedings of Conference on Problems of Decision Making Under Uncertainties, pages 54–57, 2003.Google Scholar