Decontamination of radioactive effluent with clinoptilolite /

The removal of strontium-90 and cesium-137 from fuel storage basin effluent by ion exchange using the mineral clinoptilolite as the exchanger is described. The concentration of cesium-137 in the effluent after decontamination was less than its drinking water tolerance, and the concentration of strontium-90 was approximately equal to its tolerance."National Reactor Testing Station"--Cover."Waste Disposal and Processing ; TID-4500 (42nd Ed.).""Issued: July 1965."Includes bibliographical references (p. 16).The removal of strontium-90 and cesium-137 from fuel storage basin effluent by ion exchange using the mineral clinoptilolite as the exchanger is described. The concentration of cesium-137 in the effluent after decontamination was less than its drinking water tolerance, and the concentration of strontium-90 was approximately equal to its tolerance.Work Performed by Phillips Petroleum Company for the Atomic Energy CommissionMode of access: Internet