Optimizing the dynamic response of the H. B. Robinson nuclear plant using multiobjective particle swarm optimization
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M. A. Elsays
Abstract
In this paper, the Particle Swarm Optimization (PSO) algorithm is modified to deal with Multiobjective Optimization Problems (MOPs). A mathematical model for predicting the dynamic response of the H. B. Robinson nuclear power plant, which represents an Initial Value Problem (IVP) of Ordinary Differential Equations (ODEs), is solved using Runge-Kutta formula. The resulted data values are represented as a system of nonlinear algebraic equations by interpolation schemes for data fitting. This system of fitted nonlinear algebraic equations represents a nonlinear multiobjective optimization problem. A Multiobjective Particle Swarm Optimizer (MOPSO) which is based on the Pareto optimality concept is developed and applied to maximize the above mentioned problem. Results show that MOPSO efficiently cope with the problem and finds multiple Pareto optimal solutions.
Kurzfassung
In dieser Arbeit wird der Partikel-Schwarm Optimierungsalgorithmus (PSO) modifiziert, um multiobjektive Optimierungsprobleme (MOP) zu behandeln. Ein mathematisches Modell für die Vorhersage der Leistungsfähigkeit des H. B. Robinson Kernkraftwerks, die ein Anfangswertproblem (IVP) für gewöhnliche Differenzialgleichungen (ODEs) darstellt, wurde unter Verwendung der Runge-Kutta-Gleichung gelöst. Die Ergebnisse werden dargestellt als System nicht-linearer algebraischer Gleichungen mit Interpolationsschemata für die Datenanpassung. Dieses System nicht-linearer algebraischer Gleichungen repräsentiert ein nicht-lineares multiobjektives Optimierungsproblem. Ein Multiobjektiver Partikel-Schwarm-Optimierer (MOPSO) auf der Basis des Pareto-Optimierungskonzepts wurde entwickelt und auf das beschriebene Problem angewendet. Experimentelle Ergebnisse zeigen, dass MOPSO das beschriebene Problem effizient löst und optimale, multiple Pareto-Lösungen findet.
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© 2009, Carl Hanser Verlag, München
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- Modified Chebyshev polynomial (UN) approximation in the neutron transport theory and computation of critical half thicknesses
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- Assessment for inside building dispersion of aerosol from an outdoor radiological release
- Technical Notes/Technische Mitteilungen
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- AVR prototype pebble bed reactor: a safety re-evaluation of its operation and consequences for future reactors
- Design Concept of the High Performance Light Water Reactor
- Behavior of CANDU fuel under power pulse conditions at the TRIGA reactor of INR Pitesti
- Plate heat exchanger – inertia flywheel performance in loss of flow transient
- Performance analyses of the communication networks of a modern supervision and control system of research reactors
- Thermal analytical model for MoO3 ampoules irradiated in a high neutron flux
- Effect of using various grades of plutonium in the protective liquid wall of an IFE type fusion reactor
- A discrete ordinates scheme for void fraction evaluation with nonstandard reflective conditions and weakly divergent beams
- Application of the Laplace transform method for the albedo boundary conditions in multigroup neutron diffusion eigenvalue problems in slab geometry
- Modified Chebyshev polynomial (UN) approximation in the neutron transport theory and computation of critical half thicknesses
- Optimizing the dynamic response of the H. B. Robinson nuclear plant using multiobjective particle swarm optimization
- Assessment for inside building dispersion of aerosol from an outdoor radiological release
- Technical Notes/Technische Mitteilungen
- Analysis of a steam generator tube rupture under realistic initial and boundary conditions
