1. ENDF/B-VII.1 Data File for 93Nb (MAT = 4125),2011
2. ENDF/B-VII.1 Data File for 103Rh (MAT = 4525),2011
3. ENDF/B-VII.1 Data File for 115In (MAT = 4931),2011
4. Neutron Radiation Cross-section, Neutron Transmission and Average Resonance Parameters for Some Fission Product Nuclei;Bokhovko,1991
5. Capture Cross Sections in the keV Region;Campbell,1970