New neutron-induced cross-section measurements for improved nuclear data

Many older neutron cross-section evaluations from libraries such as ENDF/B-VI or JENDL-3.2 exhibit deficiencies or do not cover energy ranges that are important for nuclear reactor and criticality safety applications. These deficiencies may occur in the resonance region and high energy region. Consequently, these evaluated data may not be adequate for radiation transport calculations where effects such as self-shielding, multiple scattering, or Doppler broadening are important. To support the U.S. Nuclear Criticality Safety Program, a series of new measurements has been undertaken in response to deficiencies identified in nuclear data libraries. New data and evaluations including covariances are required for several materials found in mixtures with uranium. For this purpose neutron capture and total cross section measurements have been