Department of Nuclear Engineering

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About Department of Nuclear Engineering

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Department of Nuclear Engineering has more than 13 academic staff members

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Some of publications in Department of Nuclear Engineering

Multi-lingual Translation of The Mathematical Secrets of Pascal's Triangle

This is a ed.Ted lesson translated by amara to 25 languages about the secrets of Pascal's triangle
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Reactor kinetics revisited: a coefficient based model (CBM)

In this paper, a nuclear reactor kinetics model based on Guelph expansion coefficients calculation ( Coefficients Based Model, CBM), for n groups of delayed neutrons is developed. The accompanying characteristic equation is a polynomial form of the Inhour equation with the same coefficients of the CBM- kinetics model. Those coefficients depend on Universal abc- values which are dependent on the type of the fuel fueling a nuclear reactor. Furthermore, such coefficients are linearly dependent on the inserted reactivity. In this paper, the Universal abc- values have been presented symbolically, for the first time, as well as with their numerical values for U-235 fueled reactors for one, two, three, and six groups of delayed neutrons. Simulation studies for constant and variable reactivity insertions are made for the CBM kinetics model, and a comparison of results, with numerical solutions of classical kinetics models for one, two, three, and six groups of delayed neutrons are presented. The results show good agreements, especially for single step insertion of reactivity, with the advantage of the CBM- solution of not encountering the stiffness problem accompanying the numerical solutions of the classical kinetics model. (author)
Wajdi Mohamed Ratemi(1-2011)
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RTC-method for the control of nuclear reactor power

In this paper, a new concept of the Reactivity Trace Curve (RTC) for reactor power control is presented. The concept is demonstrated for a reactor model with one group of delayed neutrons, where the reactivity trace curve is simply a closed form exponential solution of the RTC-differential equation identifier. An extended reactor model of multigroup (six groups) of delayed neutrons is discussed for power control using the RTC-method which is based on numerical solution of the governing equation for the RTC-differential equation identifier. In this numerical solution, an impeded analytical solution for the RTC-identifier in every sampling time step is used. Finally, the concept is applied to a more rigorous reactor model, namely; a model of multigroup of delayed neutrons with temperature feedback. The simulation studies for all of the above mentioned cases demonstrate the validity of the concept for reactor power control with absolute elimination of power shootings.
Wajdi Mohamed Ratemi (1-1998)
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