High-Frequency Titration as Applied to the Determination of Thorium, Uranium, Sulfate, and Free Acid. Parts 1-51 (open access)

High-Frequency Titration as Applied to the Determination of Thorium, Uranium, Sulfate, and Free Acid. Parts 1-51

The technique of high-frequency titrimetry was applied to the determination of thorium, uranium, sulfate, and free acid. In Part I, the reproducibility of the method for the titration of standard solutions that contained 50 rag of thorium in the absence of interferences is established. Under these conditions, the coefficient of variation of the method was <1%. In Part II, the effect of uranium on the highfrequency titration of thorium, as well as the application of the method to actual samples, is discussed. Uranium in a ratio of 5 to 1 to thorium can be tolerated. When the method is applied to the analysis of representative samples, the coefficient of variation is 1%. Attempts to determine uranium by high-frequency titration with 8-quinolinol were unsuccessful. Tests on this titration and possible reasons for its failure are discussed in Part III. The application of the high-frequency titration method to the determination of sulfate in solutions of uranyl sulfate is described in Part IV. The coefficient of variation, on titrating 40 to 70 mg of sulfate with barium chloride after the uranium is masked with citrate or fluoride, is 2%. In Part V, the high-frequency titration of free acid in solutions of uranyl sulfate …
Date: May 11, 1959
Creator: Menis, O
System: The UNT Digital Library
Metallurgy Division SemiAnnual Progress Report for Period Ending October 10, 1955 (open access)

Metallurgy Division SemiAnnual Progress Report for Period Ending October 10, 1955

Static corrosion tests in sodium and in fused-fluoride-salt mixture on type 310 stainless steel T-joints brazed with various alloys by the Wall Colmonoy Corporation indicate that the 9% Si-2.5% P-88.5% Ni alloy has fair resistance to both media.
Date: May 11, 1956
Creator: Frye, J. H.; Manly, W. D. & Cunningham, J. E.
System: The UNT Digital Library
Reprocessing of Are Fuel, Volatility Pilot Plant Runs E-1 and E-2 (open access)

Reprocessing of Are Fuel, Volatility Pilot Plant Runs E-1 and E-2

After two batches ( approximately 340 kg) of fluoride salt from the ARE were reprocessed, a pilot plant operations were terminated because of a leak through which an estimated 780 g of uranium (as UF/sub 6/ escaped. Of the 21 kg of highly enriched uranium in the feed, 93.12% was collected as UF/sub 6/ product, 0.13% represented measured losses, and 3.72% was unaccounted for (leak). An additional 3.03% was reclaimed from NaF beds and equipment washes. The produce met both chemical purity and activity specifications for product level UF/ sub 6/. Decontamination from fission products was essentially complete. A gross gamma decontamination factor was apparently limited by the low activity of the feed salt. (auth)
Date: May 11, 1959
Creator: Whitmarsh, C. L.
System: The UNT Digital Library
MEETING XVIII -- BEVATRON RESEARCH CONFERENCE -- BEVATRON OPERATION and NUCLEAR EMULSION EXPERIMENTS (open access)

MEETING XVIII -- BEVATRON RESEARCH CONFERENCE -- BEVATRON OPERATION and NUCLEAR EMULSION EXPERIMENTS

Results of preliminary tests with photographic emulsions using a lip target are discussed. Some methods for the search of heavy mesons are suggested. The preliminary tests with photographic emulsions were designed to investigate exposure conditions inside the Bevatron. These were carried out with stationary targets, since injected targets were not available at that time. The first exposure was designed to study the shielding required for emulsions placed in the direct beam (9 inches from the magnet conterline) during the entire acceleration cycle. Three 200{micro} Ilford G5 emulsions embedded in various thicknesses of brass were exposed for 30 pulses. Nominal maximum energy of beam was 3.5 Bev. During the second and third exposure (nominal maximum beam energies 4.1 and 6 Bev respectively) a lip target was placed in front of the emulsions. This was designed so as to dampen out the radial oscillations in the first section (.36 inches thick, 1/2 inch radial length). The beam should then hit the second section (.9 inches thick, .75 inch radial length) which is designed to reduce the beam orbit by {approx} 1 1/4 inches and then hit the emulsions on the next turn. 1/2 inch brass absorber was placed ahead of the emulsions.
Date: May 11, 1954
Creator: Lofgren, E.J. & Goldhaber, Gerson
System: The UNT Digital Library
Purex Pulse Generator Operation (open access)

Purex Pulse Generator Operation

None
Date: May 11, 1955
Creator: McCarthy, P. B.
System: The UNT Digital Library
Adsorption of Xenon in an Activated Charcoal Column (open access)

Adsorption of Xenon in an Activated Charcoal Column

Performance characteristics of two activated charcoal columns at room temperature in separating fission-product xenon from an air stream were investigated by installing each column in the exhaust from an enclosure in which irradiated slugs were dissolved. Breakthrough curves are presented and the variation in xenon concentration within the columns is examined. Theoretical treatments of adsorption columns in the literature are found to agree well with the experimental data. Performance of the colunms is evaluated in terms of concentration factor'' and number of effective theoretical plates. (auth)
Date: May 11, 1959
Creator: Cantelow, H. P.
System: The UNT Digital Library
An Experimental Study of Retinal Burns: Part I. The Irradiance Thresholds for Chorio-Retinal Lesions. Part II. Entoptic Scatter as a Function of Wave Length (open access)

An Experimental Study of Retinal Burns: Part I. The Irradiance Thresholds for Chorio-Retinal Lesions. Part II. Entoptic Scatter as a Function of Wave Length

Using a high intensity light source to produce chorioretinal lesions in the eyes of rabbits, cats, and guinea pigs, the authors determined, at different levels of retinal irradiance, the exposure time which produced an ophthalmoscopically visible lesion. It was found that, at irradiance levels greater than 2 cal/cm/sup 2/sec, a radiant exposure of 1.0 cal/cm/sup 2/ produced a threshold lesion. At irradiance levels less than 0.7 cal/cm/sup 2//sec, lesions could not be produced at any exposure time through ten seconds. Histological data on the nature of the legions and course of healing are presented and discussed. (auth)
Date: May 11, 1959
Creator: Demott, D. W. & Davis, T. P.
System: The UNT Digital Library
Power Reactor Fuel Reprocessing: Mechanical Phase (open access)

Power Reactor Fuel Reprocessing: Mechanical Phase

None
Date: May 11, 1959
Creator: Klima, B. B.
System: The UNT Digital Library
Uranium-Zirconium Explosions in Nitric Acid (open access)

Uranium-Zirconium Explosions in Nitric Acid

None
Date: May 11, 1953
Creator: Russell, R.B.
System: The UNT Digital Library
PROPERTIES OF STAINLESS STEEL-URANIUM DIOXIDE FUEL PLATES (open access)

PROPERTIES OF STAINLESS STEEL-URANIUM DIOXIDE FUEL PLATES

None
Date: May 11, 1954
Creator: Keeler, J. R. & Cuddy, L. J.
System: The UNT Digital Library
Interim report of N-1 tank product recoveries in the 231 Building (open access)

Interim report of N-1 tank product recoveries in the 231 Building

This report, from the Hanford Plant, May 11, 1951, describes the filtration of process solution resulting from building 231 activities.
Date: May 11, 1951
Creator: Smolen, S. G.
System: The UNT Digital Library