Studies of^54,56Fe Neutron Scattering Cross Sections

Abstract

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.

The Neutron Time-of-Flight Cross Section Program at the University of Kentucky - Adventures in Analysis II

“…Examples of results from the laboratory may be found in other presentations and papers from the CGS-15 conference, in particular, 54,56 Fe results are given in Ref. [1].…”

Neutron scattering cross section measurements forFe56

“…Despite these efforts, there are still significant discrepancies among predictions from existing evaluated data libraries, particularly for the inelastic scattering processes [13]. Such discrepancies can be attributed to experimental data that have large or non-existent uncertainties, lack of information on finite-size sample corrections, or inadequate inelastic scattering data [14]. In addition, sensitivity studies on important reactor quantities, such as criticality, require the reduction of neu- * ap.ramirez@uky.edu tron cross-section uncertainties on actinides and structural materials to meet the target accuracies for advanced reactor designs [1][2][3].…”