Parameter analysis of the neutron point kinetics equations with feedback temperature effects

• Mathematical models describing the point reactor kinetics equations of Nuclear Power Plants.
• Block diagram model for kinetic equations solution using VisSim environment.
• Comparison between both analytical and numerical solutions.
• Neutron flux density and reactor reactivity are analyzed.
• Efficient control is performed for Nuclear Power Plants.

The paper presents a solution technique for modeling point nuclear kinetic equations based on one group of delayed neutrons and temperature feedback. Explicit and implicit solutions for point kinetic equations are used for this purpose. Analytical treatment is conducted. Mathematical models describing neutron density and reactor reactivity are deduced. Also, Matlab Simulink and VisSim environments are used to achieve the implicit solution. Using of graphical user interface allows a quick experimentation with alternative values of performance parameters such as initial reactivity, initial neutron flux density, temperature coefficient of reactivity and reciprocal of thermal capacity of reactor. Moreover, implicit solutions of dynamic equations governing point nuclear kinetic equations provide exact handling of the device performance. Proposed mathematical models and block diagram simulation results are validated against published work and full agreements are obtained. Several performance parameters are tuned to enhance the performance of these point nuclear kinetic equations through the presented methodology. The resultant performance characteristics and comparison among investigated models are presented in this work. The obtained results confirm that the implicit solution showed less accurate representation of the studied point nuclear kinetic equations compared to mathematical models. Furthermore, the effect of control rod on the neutron flux density was discussed.