Calculation of the Neutron Flux Density Distribution in Two Dimensional Hexagonal Fuel Assembly of Light Water Reactor by Transmission Probability Method

The paper describes the model for calculating the neutron flux density distribution in two dimensional hexagonal geometry assembly of light water reactor(LWR) by transmission probability method. The source within the meshes is assumed to be isotropic and linearly dependent on x and y coordinates. At the mesh surfaces the constant space distribution and the simple 6P 1 approximation for the angular distribution are considered. The water gap surrounding assembly is also considered. Based on proposal model, the code TPHEX C is encoded and some problems concerned in hexagonal light water reactor assembly are calculated. The calculated results from code TPHEX C and Monto Carlo method are all in good agreement. The TPHEX C code can be used for the hexagonal geometry assembly for LWR.