Dosimetry results for big ten and related benchmarks

Measured average reaction cross sections for the Big Ten central flux spectrum are given together with calculated values based on the US Evaluated Nuclear Data File ENDF/B-IV. Central reactivity coefficients for /sup 233/U, /sup 235/U, /sup 239/Pu, /sup 6/Li, and /sup 10/B are given to check consistency of bias between measured and calculated reaction cross sections for these isotopes. Spectral indexes for the Los Alamos /sup 233/U, /sup 235/U, and /sup 239/Pu metal critical assemblies are updated, utilizing the Big Ten measurements and interassembly calibrations, and their implications for inelastic scattering are reiterated.