Inderscience Publishers

The solution of coupled fractional neutron diffusion equations with delayed neutrons

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The distribution of the neutron population in a nuclear reactor is described by using transport equations. One possible solution of the fractional neutron transport equation is given by the fractional neutron diffusion equation. This paper presents the application of an analytical approximation method for the solution of one group of fractional neutron diffusion equations with one group of delayed neutrons.

Keywords: neutron diffusion equations, neutron flux, Adomian decomposition method, delayed neutrons, nuclear reactors, transport equations, nuclear energy, nuclear power

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