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U.S. Department of Energy
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PACER: a Monte Carlo time-dependent spectrum program for generating few-group diffusion-theory cross sections

Technical Report ·
OSTI ID:6663931
The PACER Monte Carlo program for the CDC-7600 performs fixed source or eigenvalue calculations of spatially dependent neutron spectra in rod-lattice geometries. The neutron flux solution is used to produce few group, flux-weighted cross sections spatially averaged over edit regions. In general, PACER provides environmentally dependent flux-weighted few group microscopic cross sections which can be made time (depletion) dependent. These cross sections can be written in a standard POX output file format. To minimize computer storage requirements, PACER allows separate spectrum and edit options. PACER also calculates an explicit (n, 2n) cross section. The PACER geometry allows multiple rod arrays with axial detail. This report provides details of the neutron kinematics and the input required.
Research Organization:
Bettis Atomic Power Lab., Pittsburgh, PA (USA)
DOE Contract Number:
AC11-76PN00014
OSTI ID:
6663931
Report Number(s):
WAPD-TM-1518; ON: DE83003779
Country of Publication:
United States
Language:
English