New Neutron Cross-Section Measurements at ORELA for Improved Nuclear Data Calculations

Abstract

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 criticality safety applications. These deficiencies may occur in the resolved and unresolved‐resonance regions. Consequently, these evaluated data may not be adequate for nuclear criticality calculations where effects such as self‐shielding, multiple scattering, or Doppler broadening are important. To support the Nuclear Criticality Predictability Program, neutron cross‐section measurements have been initiated at the Oak Ridge Electron Linear Accelerator (ORELA). ORELA is the only high‐power white neutron source with excellent time resolution still operating in the United States. It is ideally suited to measure fission, neutron total, and capture cross sections in the energy range from 1 eV to ∼600 keV, which is important for many nuclear criticality safety applications.