The Solution of Two-Dimensional Neutron Diffusion Equation with Delayed Neutrons
Volume 12, Issue 2 (2001), pp. 337–342
Pub. online: 1 January 2001
Type: Research Article
Received
1 November 2000
1 November 2000
Published
1 January 2001
1 January 2001
Abstract
The distribution of neutron population in nuclear reactor is described by using transport equations. One of possible approximations of neutron transport equation is given by the neutron diffusion equation. The paper presents numerical solution method of one group neutron diffusion equation with one group of delayed neutrons.