CENTRM

 

CENTRM computes continuous-energy neutron spectra using 1-D discrete ordinates or infinite media geometry. CENTRM determines the problem-specific fluxes for processing resonance-shielded multigroup data using a 1-D unit cell, and then utilizing the spectrum as a problem-dependent weight function for multigroup averaging. The multigroup data processing is done by the PMC code, which reads the CENTRM continuous-energy flux spectra and cross-section data; calculates problem-dependent, group-averaged cross sections over some specified energy range; and then replaces the corresponding data in an input AMPX master library.