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2012 (Vol. 4, Issue: 08)
Article Information:

Approximate Solution of the Point Reactor Kinetic Equations of Average One-Group of Delayed Neutrons for Step Reactivity Insertion

S. Yamoah, M. Asamoah and P. Asiedu-Boateng
Corresponding Author:  S. Yamoah 

Key words:  Analytical, Laplace transform, neutron population, point reactor kinetic, reactivity, time-dependent,
Vol. 4 , (08): 892-896
Submitted Accepted Published
October 12, 2011 November 18, 2011 April 15, 2012

The understanding of the time-dependent behaviour of the neutron population in a nuclear reactor in response to either a planned or unplanned change in the reactor conditions is of great importance to the safe and reliable operation of the reactor. In this study two analytical methods have been presented to solve the point kinetic equations of average one-group of delayed neutrons. These methods which are both approximate solution of the point reactor kinetic equations are compared with a numerical solution using the Eulerís first order method. To obtain accurate solution for the Euler method, a relatively small time step was chosen for the numerical solution. These methods are applied to different types of reactivity to check the validity of the analytical method by comparing the analytical results with the numerical results. From the results, it is observed that the analytical solution agrees well with the numerical solution.
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  Cite this Reference:
S. Yamoah, M. Asamoah and P. Asiedu-Boateng, 2012. Approximate Solution of the Point Reactor Kinetic Equations of Average One-Group of Delayed Neutrons for Step Reactivity Insertion.  Research Journal of Applied Sciences, Engineering and Technology, 4(08): 892-896.
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ISSN (Online):  2040-7467
ISSN (Print):   2040-7459
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