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A 50-group, 101-isotope library of multigroup constants for nuclear reactor design is described. Nuclear cross sections, self-shielding factors, transfer matrices, and delayed neutron data were generated with MINX and NJOY using evaluated data from ENDF/B-IV. The output is in the CCCC-III interface format. Test results are presented for six CSEWG benchmark critical assemblies.

LIB-IV, a library of group constants for nuclear reactor calculations. [50-group, 101-isotope library generated with MINX from ENDF/B-IV]