Abstract
Elastic and inelastic neutron scattering differential cross sections and γ-ray production cross sections have been measured on 54,56 Fe at several incident energies in the fast neutron region between 1.5 and 4.7 MeV. All measurements were completed at the University of Kentucky Accelerator Laboratory (UKAL) using a 7-MV Model CN Van de Graaff accelerator, along with the neutron production and neutron and γ-ray detection systems located there. The facilities at UKAL allow the investigation of both elastic and inelastic scattering with nearly mono-energetic incident neutrons. Time-of-flight techniques were used to detect the scattered neutrons for the differential cross section measurements. The measured cross sections are important for fission reactor applications and also for testing global model calculations such as those found at ENDF, since describing both the elastic and inelastic scattering is important for determining the direct and compound components of the scattering mechanism. The γ-ray production cross sections are used to determine cross sections to unresolved levels in the neutron scattering experiments. Results from our measurements and comparisons to model calculations are presented.
Highlights
The design and implementation of next-generation fission reactors is important for meeting our long-term energy needs
Neutron elastic and inelastic scattering cross sections for materials used in the reactor environment are important for designs that most efficiently produce nuclear power safely
Neutron inelastic scattering cross sections are very important for determining the direct component of the reaction mechanism
Summary
The design and implementation of next-generation fission reactors is important for meeting our long-term energy needs. Neutron elastic and inelastic scattering cross sections for materials used in the reactor environment are important for designs that most efficiently produce nuclear power safely. Data evaluations are used to supply the needed cross sections to design engineers, but often the models used to determine the evaluations are based on experimental measurements that have large or nonexistent uncertainties, little information on corrections for finite-sample effects, and/or the incident neutron energies represented in the existing data are sparse and, in many cases, non-existent for inelastic neutron scattering. Cross sections that are most needed for fission reactor design have been tabulated [1]. To provide neutron cross sections in the fast neutron energy region, a series of new neutron scattering measurements have been made at the University of Kentucky and are discussed here
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