NDC A FORTRAN PROGRAM FOR UNIT CELL NUCLEAR DESIGN CALCULATIONS FOR ROD-CLUSTERED PRESSURE-TUBE LATTICES VOLUMEⅠ. PROGRAM FORMULATION AND APPLICATION

摘要

The NDC (Nuclear Design Calculations) Program has been developed - in FORTRAN for use on the IBM-704/709/7090 - to compute the reactivity and turnup properties of pressure-tube lattices with clustered fuel rods by applying the unit cell method. The required input consists of the fuel assembly and the tube lattice geometry, the material distributions and some physical data.nThe unit cell analysis is applied to a piecewise homogeneous, cylindrical, equivalent model of the actual reactor structure. The Amouyal-Benoist method is used to obtain the thermal utilization. The Dancoff correction and the Doppler factor is applied in evaluating the resonance integral for the fissionable materials. The Spinrad approach is used to compute the fast fission factor. The resonance fissions feedback is taken into account in the neutron cycle. Only the U-Pu series is considered in the cell-homogenized depletion calcula¬tions.