استفاده از روش بسط نودال در محاسبات قلب رآكتورهاي با مجتمع سوخت مربعي

Using Nodal Expansion Method in Calculation of Reactor Core with Square Fuel Assemblies

A polynomial nodal method is developed to solve few-group neutron diffusion equations in cartesian geometry. In this article, the effective multiplication factor, group flux and power distribution based on the nodal polynomial expansion procedure is presented. In addition, by comparison of the results the superiority of nodal expansion method on finite- difference and finite-element are fully demonstrated. The comparison of the results obtained by these method with those of the well known benchmark problems have shown that they are in very good agreement.