1. Group Constants for Nuclear Reactor Calculations;Bondarenko,1964
2. MIGROS-3: a code for the generation of group constants for reactor calculations from neutron nuclear data in KEDAK format;Broeders,1977
3. Temperature-dependent transmission and self-indication measurements upon depleted U in the unresolved region;Byoun,1972
4. Application of the Probability Table Method to Multigroup Calculations of Neutron Transport
5. Program GROUPIE (Version 79-1): calculation of Bondarenko self-shielded neutron cross sections and multiband parameters from data in the ENDF/B format;Cullen,1980