APWRC-CELCOR, A FORTRAN-II PROGRAM FOR MULTIPLE LETHARGY LEVEL P1 OR DSN CELL CORRECTIONS IN CYLINDRICAL, SPHERICAL AND ONE- OR TWO-DIMENSIONAL SLAB GEOMETRY

Technical Report · Thu Mar 01 04:00:00 EST 1962

OSTI ID:4827948

Olsen, T M; Cannon, G A; Colbeth, E A; Frederick, D H; Kutz, W P; Schaefer, E A

A description of the nuclear analysis code, CELCOR, a FORTRAN-II program for the IBM 7090 computer is preseated. GELCOR calculates mulitiple lethargy level cell corrections for spherical, cylindrical, or slab cells. For the slab case, a two-dimensional synthesis option is available, allowing consideration of the flux distribution, beth perpendicular and parallel to the plane of the slab. Flux distributions may be calculated using P1 or SN options; S2, S4, S6, S8, and S16 approximations are available in all geometries except cylindrical, where storage requirements limited the highest order to S8. Comparisons are given of CELCOR analyses with experimental results. The latter include experimental fine activation distributions through a unit cell, heterogeneous-homogeneous fuel element substitation experiments, and assembly of clean critical configurations. A complete coverage of input and outpat, operating instructions, sample problem, equations and a program listing are included. (auth)

• Research Organization: Martin Co. Nuclear Div., Baltimore
• NSA Number: NSA-16-021721
• OSTI ID: 4827948
• Report Number(s): MND-C-2500-2
• Country of Publication: United States
• Language: English

Related Subjects

COMPUTERS
CONFIGURATION
CRITICAL ASSEMBLIES
CYLINDERS
DIFFERENTIAL EQUATIONS
DISTRIBUTION
FUEL ELEMENTS
HOMOGENEOUS REACTORS
MATHEMATICS
MEASURED VALUES
NEUTRON FLUX
NEUTRONS
PLATES
PROGRAMMING
REACTOR CORE
REACTOR TECHNOLOGY
SLOWDOWN
SPHERES