Release of ENDF/B-Ⅷ.1-based Continuous-Energy Neutron Cross-Section Data Tables for MCNP

摘要

The release of the ENDF71x library represents five years of work updating ENDF/B-Ⅶ.0 to ENDF/B-Ⅶ.1 followed by a full years worth of work by the Nuclear Data Team at LANL. The library was processed from ENDF/B-Ⅶ.1 evaluations into ACE data tables using NJOY 99.393 for seven temperatures.The ENDF71x library has been heavily tested and verified [11]. The ENDF71x library is recommended for use in all Monte Carlo applications with the caveats detailed in this summary and in the complete documentation [7].