Home Courses Understanding Nuclear Energy Course materials Lectures 2.2 The Neutron Diffusion Equation

2.2 The Neutron Diffusion Equation

Course subject(s) 2. Nuclear Fission Reactor Principles

In this lecture video, Prof. Jan Leen Kloosterman will introduce you to the neutron transport equation described by diffusion theory for the one-group (energy) approximation. Using this, you can estimate the power produced by the nuclear reactor.

Keywords: neutron flux, reaction rate, neutron current density, Fick’s law, Hoger Onderwijs Reactor (HOR)

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