Neutron Diffusion Theory

Neutron Diffusion Theory - NEUTRON DIFFUSION THEORY M...

Info icon This preview shows pages 1–4. Sign up to view the full content.

View Full Document Right Arrow Icon
NEUTRON DIFFUSION THEORY © M. Ragheb 11/18/2007 1. INTRODUCTION The diffusion theory model of neutron transport plays a crucial role in reactor theory since it is simple enough to allow scientific insight, and it is sufficiently realistic to study many important design problems. The neutrons are here characterized by a single energy or speed, and the model allows preliminary design estimates. The mathematical methods used to analyze such a model are the same as those applied in more sophisticated methods such as multigroup diffusion theory, and transport theory. The derivation of the diffusion equation will depend on Fick’s law, even though a direct derivation from the transport equation is also possible. The Helmholtz equation is derived, and the limitations on diffusion equation as well as the boundary conditions used in its application to realistic problems are discussed. 2. TRANSPORT CROSS-SECTION The effect of the scattering angular distribution on the motion of a neutron is taken into account by use of the transport cross section. Let us assume: 1. An infinite medium. 2. A purely scattering medium without absorption. 3. The energy of the neutron does not change as a result of a collision with the nuclei of the medium. 4. After each collision the particle travels a scattering mean free path λ s and is deflected by an angle θ . After injection to the system, the neutron moves a distance: s Z λ = 0 (1) the projected distance traveled after the first collision along the z-axis is, as shown in Fig. 1: ) cos( 1 1 θ λ s Z = The average value of is: 1 Z µ λ θ λ s s Z = = ) cos( 1 1 (2)
Image of page 1

Info iconThis preview has intentionally blurred sections. Sign up to view the full version.

View Full Document Right Arrow Icon