skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: SPAN4; a point-kernel shield evaluation code. [CDC6600; FORTRAN IV and ASCENT]

Technical Report ·
OSTI ID:6365485

SPAN4 calculates the fast neutron dose rate, thermal neutron flux, gamma-ray flux, dose rate, and energy-absorption rate in rectangular, cylindrical, and spherical geometries by integrating appropriate exponential kernels over a source distribution. The shield configuration is flexible--a first-level shield mesh, using any one of the three geometries, is specified. Regions of this same geometry or of other geometries, having their own (finer) meshes, may then be embedded between the first-level mesh lines, defining second-level shield meshes. This process is telescopic--third-level shield meshes may be embedded between second-level meshlines in turn. All meshes may have variable spacing. Sources and detectors may be located arbitrarily with respect to any shield mesh. The source is defined by the function: s=s0+s1(a)*s2(b)*s3(c)+s4(a,b)*s3(c)+s5(a,c)*s2(b)+s6(b,c) *s1(a)+s7(a,b,c) where a, b, and c represent coordinates. If any factor is missing, the corresponding terms are zero. Cross sections, buildup factors, standard compositions, energy structures, dose-conversion factors, infinite line and infinite plane source kernels, and quadratures are contained in a library of approximately 10,000 items.CDC6600; FORTRAN IV and ASCENT; SCOPE 3.1; 64K central memory and one system disk. Microfilm is required if the plot options are to be used.

Research Organization:
Westinghouse Electric Corp., West Mifflin, PA (USA). Bettis Atomic Power Lab.
OSTI ID:
6365485
Report Number(s):
ANL/NESC-462R; ON: DE83048462
Country of Publication:
United States
Language:
English