FFTF reactor characterization program review

This report summarizes the status of the Reactor Characterization Program being conducted at the Fast Flux Test Facility, a 400 MWth sodium-cooled fast reactor designed to test fuels and materials for the United States' Liquid Metal Fast Breeder Reactor Program. A series of calibration experiments was conducted in a dry, in-reactor thimble located near the center of the reactor. As a result of the calibration measurements, goal accuracies can be met for follow-on detailed neutronic characterization. Quantities of interest include fissionable nuclei fission and capture rates, non-fission reaction rates, neutron flux spectra, power distribution and burnup. Ten characterizer assemblies were irradiated for eight days at full power; test assembly handling has been completed. Test fuel pins and dosimeters from the full power irradiation are undergoing laboratory analysis.