In-plant test measurements for spent fuel storage at Morris Operation: Volume 1. Gaseous radionuclides release rates

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Abstract
This volume is one of a series of topical reports that summarize task activities and accomplishments by the General Electric Company for engineering and test support in the potential application of Morris Operation to the DOE Away-From-Reactor Spent Fuel Storage Program. In this volume the experimentally determined release rates for tritium and krypton-85 from spent fuel storage activities at General Electric's Morris Operation were determined to be 0.3 and 3.5 curies per year, respectively. The measured concentrations of tritium and krypton-85 in the effluent air are 25/sup 0/ and 34 times lower than the respective maximum permissible concentrations for unrestricted areas. The tritium (as HTO) was collected in condensate from the air leaving the two major water storage areas. The concentration of tritium in the condensate was found by liquid scintillation measurements, and the release rate for tritium was calculated from the condensate data using isotope dilution methods. The kypton was collected by compressing a sample of the basin area exhaust air. The krypton was separated by liquefication followed by a gas chromatographic technique, and measured using an internal GM counter.

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