Chemical Technology Division, Unit Operations Section Monthly Progress Report for January 1959

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Two alternate systems, acetic acid-nickel and acetic acid-cobalt, were examined for possible replacement of the corrosion system: ferric chloride-nickel which is being used in the current transpiration corrosion protection studies. Two Fluorox fluidized bed runs were made, of 9 and 58 hr duration, in which dry air and oxygen were used as oxidizing and fluidizing gases. Tests of the hydroclone classification of thoria indicated that more than 95% of the +0.5 micron particles can be removed from a sample if 50% recovery of the -0.5 micron particles is acceptable. Fluidized bed denitration of ThNT did not produce large dense ThO/sub … continued below

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72 pages

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Bresee, J. C.; Haas, P. A.; Horton, R. W.; Watson, C. D. & Whatley, M. E. April 30, 1959.

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Two alternate systems, acetic acid-nickel and acetic acid-cobalt, were examined for possible replacement of the corrosion system: ferric chloride-nickel which is being used in the current transpiration corrosion protection studies. Two Fluorox fluidized bed runs were made, of 9 and 58 hr duration, in which dry air and oxygen were used as oxidizing and fluidizing gases. Tests of the hydroclone classification of thoria indicated that more than 95% of the +0.5 micron particles can be removed from a sample if 50% recovery of the -0.5 micron particles is acceptable. Fluidized bed denitration of ThNT did not produce large dense ThO/sub 2/ particles, but flame denitration of mixed thorium-uranium- aluminum nitrates produced spherical particles. Three alternate batch Darex flowsheets gave chloride removal to less than 350 ppm with 61% nitric acid feed, while dissolution studies of APPR fuel elements showed that complete dissolution of braze metal in aqua regia may be difficult. Leaching studies of unirradiated UO/sub 2/ pellets showed that the most important variable effecting dissolution rate was the total nitrate content of the dissolvent. Delivery of tae SRE decanning equipment was scheduled for April 1, 1959. Temperatare increases in cylinders of solid radioactive waste were calculated for APPR fuel processing using a Darex flowsheet and cooling times ranging from 1 to 8 yr. (auth)

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  • Other Information: Orig. Receipt Date: 31-DEC-60

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  • April 30, 1959

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Bresee, J. C.; Haas, P. A.; Horton, R. W.; Watson, C. D. & Whatley, M. E. Chemical Technology Division, Unit Operations Section Monthly Progress Report for January 1959, report, April 30, 1959; Tennessee. (https://digital.library.unt.edu/ark:/67531/metadc877488/: accessed July 16, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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