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- W1504189097 abstract "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." @default.
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- W1504189097 date "1982-03-02" @default.
- W1504189097 modified "2023-09-27" @default.
- W1504189097 title "FFTF reactor characterization program review" @default.
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