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Introduction

In this chapter we discuss the fundamental basis for modeling the neutron flux and hence power distribution in reactor design. Since this basis is based on the so-called multi-group treatment we will present a short derivation of the multi-group equations. After this we will concentrate on the steady-state 1-D form of the multi-group equations and discretize these equation in order to facilitate computer solution. The discrete equations are investigated in regard to mathematical properties which are used to select numerical methods capable of solving the problem. Finally, we discuss how to calculate the power distribution from the flux solution and how one chooses a suitable computational grid for the discrete calculations.

 
 

 
 

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