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Abstract
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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
Submitted: October 12, 2011
Accepted: November 18, 2011
Published: April 15, 2012 |
Abstract:
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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 Euler’s 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.
Key words: Analytical, Laplace transform, neutron population, point reactor kinetic, reactivity, time-dependent,
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Cite this Reference:
S. Yamoah, M. Asamoah and P. Asiedu-Boateng, . 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, (08): 892-896.
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ISSN (Online): 2040-7467
ISSN (Print): 2040-7459 |
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