Conceptual study on diffusion and moderation of neutron in nonmultiplying and multiplying medium in nuclear reactor have been conducted by using mathematical explanation, experimental data and graphical representation. The corresponding governing equations have been explained. A brief discussion on neutron and criticality of a reactor is carried on. Necessity of a moderator medium in slow reactors has been discussed. Comparative analysis of usefulness and drawbacks as moderator for different medium (Graphite, Beryllium, light water, heavy water and Lithium Fluoride) have been studied in aspects of different features. Mathematical example of calculating numbers of collision required for thermalization process is shown. A primary starter source is introduced in the reactor to start the initial fission reaction. Once critical condition is reached chain reaction is established. Neutron is diffused from high to low concentration area according to Fick’s law of diffusion. While going through the moderator medium fast neutron are slowed down. It is found that Fermi age and thermal diffusion length of neutron is smaller in light and heavy water than graphite or beryllium. Thus light and heavy water are effective moderator and are used conveniently in nuclear reactors.
Diffusion, Moderation, Nonmultiplying Medium, Multiplying Medium, Fermi Age Equation.
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