1. An investigation for an optimized neutron energy-group structure in thermal lattices using particle swarm optimization;Akbari;Ann. Nucl. Energy,2012
2. ENDF/B-VII.0: next generation evaluated nuclear data library for nuclear science and technology;Chadwick;Nucl. Data Sheets,2006
3. Advanced burner test reactor preconceptual design report. Argonne National;Chang;Laboratory,2006
4. Devan, K., Pandikumar, G., Venkat, G., et al., 2002. IGC-S3: A 217 group (175n, 42γ) coupled cross section set from ENDF/B-VI. Indira Gandhi Centre for Atomic Research, Report RPD/NDS/99.
5. ENDF-102, data formats and procedures for the evaluated nuclear data file, ENDF;Garber,1975