The final report is a revision and extension of the technical interim report. Individuals providing written material for the final report are listed as co-authors. Other individuals who participated substantially in compiling the final report include c. T. Bishop, R. Brown,
A procedure for the determination of uranium isotopes in water has been developed at Mound Facility. The procedure consists of coprecipitation of uranium with ferrous hydroxide, a nitric-hydrofluoric acid dissolution if the sample contains sediment, separation of the uranium by anion exchange in hydrochloric acid, electrodeposition, and alpha pulse height analysis. After a single-laboratory evaluation at Mound, the present procedure was collaboratively tested by seven other laboratories. A copy of the procedure and four water samples, ranging from 1 to 2000 disintegrations per minute (dpm) of uranium per litre of water, were sent to the participating laboratories. Two of these samples were taken from actual effluents discharged to the environment and the third was a spiked “substitute ocean water” sample. The fourth sample contained “diluted pitchblende ore” of a known uranium concentration added to a litre of deionized water. Data from the seven collaborating laboratories have been evaluated. The average uranium concentrations determined by these laboratories agreed with the reference values to within 5 percent, and the average tracer recovery was 70 percent. The precision of the results approached counting statistics error for the three water samples which did not contain sediment.
Using a sodium iodide detector and multichannel analyzer system and an underwater collimator assembly, Co-60 concentrations were determined for 548 L-Reactor Disassembly Basin cobalt slugs and slabs and 18 curium sampler slugs. The total activity of all of the assayed slugs summed to 31,783 curies. From the Co-60 concentrations of the curium sampler slugs, the irradiation flux was determined for the known irradiation time. The amounts of 239,240,241,242;243;244 produced were then obtained based on the original amount of Pu-239 irradiated.
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