Calculation of reactor physics parameters of power reactor fuel assembly in the presence of control rods

In the present work, the physical parameters for the critical calculations have been achieved using international codes in order to determine the neutron flux and power distributions in the reactor core of power reactor. The calculations of the macroscopic cross sections and diffusions coefficients at different energy groups have been preformed using the cell calculation code ( WIMS-D4 ) for power reactor core TMI-1. The criticality search and determination of neutron flux and power distributions have been carried out with the diffusion cods DAIXY and SQUID respectively. The present study shows that the super cell technique is the best way to handle the physical parameters for the power reactor core in the presence of control material in the fuel assembly such as the control rods, burnable absorber, and soluble absorber as poison materials. ( 19 tabs., 26 figs., 27 refs. )