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Robust observer based control for axial offset in pressurized-water nuclear reactors based on the multipoint reactor model using Lyapunov approach

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Published/Copyright: October 20, 2017
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Kerntechnik
From the journal Kerntechnik Volume 82 Issue 5

Abstract

In nuclear reactor imbalance of axial power distribution induces xenon oscillations. These fluctuations must be maintained bounded within allowable limits. Otherwise, the nuclear power plant could become unstable. Therefore, bounded these oscillations is considered to be a restriction for the load following operation. Also, in order to design the nuclear reactor control systems, poisons concentrations, especially xenon must be accessible. But, physical measurement of these parameters is impossible. In this paper, for the first time, in order to estimate the axial xenon oscillations and ensures these oscillations are kept bounded within allowable limits during load-following operation, a robust observer based nonlinear control based on multipoint kinetics reactor model for pressurized-water nuclear reactors is presented. The reactor core is simulated based on the multi-point nuclear reactor model (neutronic and thermal-hydraulic). Simulation results are presented to demonstrate the effectiveness of the proposed observer based controller for the load-following operation.

Kurzfassung

Die durch Schwankungen der axialen Leistungsverteilung in Kernreaktoren erzeugten Xenon-Oszillationen müssen in zulässigen Grenzen gehalten werden, da es sonst zu einem Leistungsabfall kommt. Die Begrenzung der Oszillationen muss bei der Lastnachführung berücksichtigt werden. Bei der Auslegung der Regelungssysteme von Kernreaktoren muss insbesondere die Xenonkonzentration zugänglich sein. Die physikalische Bestimmung dieser Parameter ist nicht möglich. In dem vorliegenden Beitrag wird deshalb zur Bestimmung der Xenonoszillationen und ihrer Begrenzung bei der Lastnachführung erstmalig ein Robust-Observer-System auf der Basis des Multipoint-Reaktormodells für DWR vorgestellt. Der Reaktorkern wird mit Hilfe des Multipoint-Reaktormodells sowohl in Bezug auf das Verhalten der Neutronen wie auch in Bezug auf das thermohydraulische Verhalten simuliert. Die Ergebnisse der Simulation zeigen die Effektivität der vorgeschlagenen Regelungssystems bei der Lastnachführung.

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Received: 2017-02-14
Published Online: 2017-10-20
Published in Print: 2017-10-26

© 2017, Carl Hanser Verlag, München

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Technical Contributions/Fachbeiträge
  6. Modelling Human Resource Requirements for the Nuclear Industry in Europe
  7. Some uncertainty results obtained by the statistical version of the KARATE code system related to core design and safety analysis
  8. The integrity of NSSS and containment during extended station blackout for Kuosheng BWR plant
  9. Experimental investigation of effect of spacer on two phase turbulent mixing rate in subchannels of pressure tube type BWR
  10. Thermal-hydraulic analysis of research reactor core with different LEU fuel types using RELAP5
  11. The application of knowledge management and TRIZ for solving the safe shutdown capability of fire alarms in nuclear power plants
  12. Dose assessment for emergency workers in early phase of Fukushima Daiichi nuclear power plant accident
  13. Anti-neutrino flux in a research reactor for non-proliferation application
  14. Friction coefficient and limiter load test analysis by flexibility coefficient model of Hold-Down Spring of nuclear reactor vessel internals
  15. Robust observer based control for axial offset in pressurized-water nuclear reactors based on the multipoint reactor model using Lyapunov approach
  16. Internal and external hazards inside the containment in case of an emergency situation
  17. Slab albedo for linearly and quadratically anisotropic scattering kernel with modified FN method
https://doi.org/10.3139/124.110786

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Technical Contributions/Fachbeiträge
  6. Modelling Human Resource Requirements for the Nuclear Industry in Europe
  7. Some uncertainty results obtained by the statistical version of the KARATE code system related to core design and safety analysis
  8. The integrity of NSSS and containment during extended station blackout for Kuosheng BWR plant
  9. Experimental investigation of effect of spacer on two phase turbulent mixing rate in subchannels of pressure tube type BWR
  10. Thermal-hydraulic analysis of research reactor core with different LEU fuel types using RELAP5
  11. The application of knowledge management and TRIZ for solving the safe shutdown capability of fire alarms in nuclear power plants
  12. Dose assessment for emergency workers in early phase of Fukushima Daiichi nuclear power plant accident
  13. Anti-neutrino flux in a research reactor for non-proliferation application
  14. Friction coefficient and limiter load test analysis by flexibility coefficient model of Hold-Down Spring of nuclear reactor vessel internals
  15. Robust observer based control for axial offset in pressurized-water nuclear reactors based on the multipoint reactor model using Lyapunov approach
  16. Internal and external hazards inside the containment in case of an emergency situation
  17. Slab albedo for linearly and quadratically anisotropic scattering kernel with modified FN method
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