Battelle’s Columbus Laboratories Reactor Vessel Surveillance Service Activities

This paper describes the current methodology in use at Battelle’s Columbus Laboratories for obtaining and processing pressure vessel surveillance data, extrapolating mechanical behavior, and calculating reactor coolant pressure-temperature operating curves. Recent results from the Arkansas Nuclear One—Unit 2 (ANO-2) benchmark cavity dosimetry experiment are reported. The results indicate that it is possible to calculate the flux in ex- vessel locations with accuracies on the order of 10-15 percent. Also, end of life metallurgical predictions for the Poolside Facility (PSF) Blind Test materials are compared with experimental data.