INEL integral data-testing report for ENDF/B-V dosimeter cross sections

An integral data-testing study done at the Idaho National Engineering Laboratory (INEL) for ENDF/B-V dosimeter cross sections is documented. The integral data base used is a set of spectrum-averaged cross sections derived from integral reaction rates measured for 23 dosimeter reactions. The measured integral reaction-rate data were obtained from irradiation experiments in the fast neutron field of the Coupled Fast Reactivity Measurements Facility (CFRMF). Up-to-date values for the integral reaction rates are compiled and the derivation of a consistent set of spectrum-averaged cross sections is documented. The central neutron field of the CFRMF is characterized and specified by including the results of neutronics calculations with ENDF/B-IV and ENDF/B-V nuclear data, active neutron spectrometry measurements, and a sensitivity and uncertainty analysis for the spectrum. A scheme for generating 620-group fluxes from the 68-group fluxes obtained from a transport calculation is described. Results of the following computations are included here: (1) calculations of spectrum-averaged cross sections for various CFRMF flux spectra, cross-section data bases and different weighting functions, (2) estimation of the flux and dosimeter cross-section uncertainty contributions to the uncertainty in the calculated integral cross sections, and (3) characterization of the energy response for each dosimeter reaction in the CFRMF. Integral tests, as defined by the ratio of calculated-to-measured integral cross sections, are assessed for each dosimeter reaction with respect to reaction energy response, uncertainty considerations, spectrum shape changes and weighting function effects