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NDC--A FORTRAN PROGRAM FOR UNIT CELL NUCLEAR DESIGN CALCULATIONS FOR ROD- CLUSTERED PRESSURE TUBE LATTICES. VOLUME I. PROGRAM FORMULATION AND APPLICATION. VOLUME II. PROGRAM COMPOSITION AND LISTING

Technical Report ·
OSTI ID:4666485
The NDC (Nuclear Design Calculations) Program was developed in FORTRAN for use on the IBM-704/709/7090 to compute the reactivity and burNonenup 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. The unit cell anaiysis is applied to a piecewise homogeneous, cylindrical, equivalent model of the actual reactor structure. The AmouyalBenoist 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 calculations. The program output includes the equivalent cylindrical geometry, the various cross sections, the criticality factors, the initial conversion ratio, and the burnup results. Provision for temperature and void coefficients evaluation is made. A 32 k machine is required. Typical problem running times on the IBM-7090 are of the order of a minute. (auth)
Research Organization:
Westinghouse Electric Corp. Atomic Power Div., Pittsburgh
NSA Number:
NSA-17-033238
OSTI ID:
4666485
Report Number(s):
CVNA-146(Vol.I & II)
Country of Publication:
United States
Language:
English