Climax spent-fuel dosimetry. Progress report, September 1981-September 1982

Data from the second exchange of dosimeters from the Climax Spent Fuel Test Facility were evaluated for gamma-ray and neutron exposures. The data followed the previous trend of significant disagreement between the various exposures derived from measurements of different absorption peaks. The effects of temperature during irradiation were investigated and shown to be the major, if not the only, cause of the differences observed and commented on in the previous data collected last year. New data concerning irradiation temperature can be used to eliminate from consideration any neutron-caused effects, of at least a gross magnitude, at the Climax facility. Corrected data taking into account the effects of temperature during irradiation are provided for last year`s data as well as for the current year. The gamma-ray data show an overall decline in integrated dose, as expected from decay considerations. The neutron data are less consistent, with some apparent spectral shifts with time. The 247-nm and 374-nm absorption peaks in LiF chips can provide dosimetry coverage from 10{sup 4} to 10{sup 8} rads-LiF. Calibration data at 25 to 30{sup 0}C have verified that the dosimetry system is essentially temperature-independent over this range. The neutron fluence at the facility is small but measurable, and produces little effect on the gamma-ray dosimeters