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Description: The cation exchange characteristics of several commercially available zeolites were evaluated, Equilibrium loading characteristics and exchange capacities were determined experimentally in the binary systems cesium-lithium, cesium-- sodium, cesium--potassium, cesium-Tubidium, cesium -- hydrogen, cesium-- ammonium, strontium-- magnesium, strontium-- calcium, strontium-- barium, and strontium-- hydrogen for several zeolites. Exchangeable cation fractions in the equilibrium solutions were varied from 0.2 to 0.00001, while the total normality of the system constituents was held constant. Results were plotted as equivalent fraction of the traced cation on the zeolite at equilibrium vs. the fraction of traced cation remaining in the equilibrium solution. If an influent composition is known, and falls in the system listed above, zeolite column loading may be read directly in univalent-univalent or divalent-divalent systems. However, in the strontium-sodium or strontium-- hydrogen systems, a k value must be used because squared terms appear in the equilibrium expression as follows: 2 Na- zeolite plus or minus Sr-solution in equilibrium 2 Nasolution + Sr-zeolite, or k = (Sr-zeolite)(Na-solution)/ (Na-zeolite)2(Sr-solution). The k for a given cation is a function of zeolite loading with that cation. Several column 50% loading capacities were determined to randomly test the validity of the above curves to predict column capacities, Several columns loaded with known amounts of cesium and strontium radioisotopes were heated to 800 deg C for 24 hours to simulate a zeolite packaging dehydration cycle. Losses of cesium and strontium activity during the 24-hr period were determined. Elution of the remaining activity on the columns was accomplished with various eluting agents including dilute HNO/sub 3/, NH/sub 4/NO/sub 3/, CaCl/sub 2/ and La(NO/su b 3/)/sub 3/, and elution curves were calculated. (auth)
Date: August 10, 1962
Creator: Ames, L.L. Jr. & Knoll, K.C.
Partner: UNT Libraries Government Documents Department

Chemical Processing Technology Quarterly Progress Report, April-June 1961

Description: The Idaho Chemical Processing Plant did not operate on fuel recovery during this period, due to extensive renovation and modiflcation of facilities. Potasslum fluoride was found to be an undesirable additive to the barium precipitating agent used in formation of barium fluozirconate, because of precipitation and loss of uranium, although essentially complete precipitation of zirconium was achieved. Addition of hydrofluoric acid with barium precipitant, to achieve a fluoride/zirconium mole ratio of 5.5, was found to give a total zirconium recovery of 05%, including approximately 10% recovered after concentration of the supernate from the original precipitation. Removal of 97% of the zirconium and fluoride from zirconium -uranium dissolver solutions was achieved by precipitation with two moles of sodium formate per mole of zirconium. Uranium was readily recovered from the concentrated filtrate and wash solution by TBP extraction. The preparation and characterization of zirconium nitrate dibutylphosphate are described, and the solubility in Amsco was found to be similar to that of the uranlum dibutylphosphate complex (2 to 4 x 10/sup -5/ M). Stability studies indicated very little, if any, oxidation of ferrous to ferric iron ln a normal raffinate environment, and ferrous iron has a very low molar extinction coefficsent (0.8) compared with that of uranium (15) in the spectral region near 415 m mu . Pilot plant studies of the fluidized-bed calcination process for reduction of radioactive liquld wastes to the more-easily-stored solid form was continued in the two-foot-square calciner with production, for the first time over a prolonged period of continuous operation, of alpha alumina-free product from a feed contalning substantial sodium. Intra-particle porosities ranging from 0.04 to 0.60 were obtained. Differences in alpha-forming tendency of amorphous aluminas with varied calcination histories were demonstrated but attempts at correlation with known variables in fluid bed calciner operation were not successful. Rapid ...
Date: November 10, 1961
Creator: Bower, J. R.
Partner: UNT Libraries Government Documents Department


Description: Methods were developed for the syntheses of alkalimetal p--bar ethylbenzenesulfonates. P--bar ethylbenzenesulfonic acid is isolated and is purified as barium p--bar -ethylbenzenesulfonate which is converted to the Na, K, or Cs p-bar -ethylbenzenesulfonate by means of a slight excess of the corresponding alkali-metal carbonate. Lithium sulfate is used to form the lithium p-bar -ethylbenzenesulfonate. (auth)
Date: March 30, 1962
Creator: White, J.C. & Holsopple, H.L.
Partner: UNT Libraries Government Documents Department