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  Partner: UNT Libraries Government Documents Department
 Decade: 1940-1949
 Year: 1947
Abstracts of Research and Development Reports

Abstracts of Research and Development Reports

Date: September 1, 1947
Creator: AEC
Description: None
Contributing Partner: UNT Libraries Government Documents Department
Experiments to Test the Validity of the Linear R-Dose/Mutation Frequency Relation in Drosophila at Low Dosage

Experiments to Test the Validity of the Linear R-Dose/Mutation Frequency Relation in Drosophila at Low Dosage

Date: January 1, 1947
Creator: Spencer, W.P. & Stern, C.
Description: None
Contributing Partner: UNT Libraries Government Documents Department
Distribution of Boron in Processing of Carnotite Concentrate

Distribution of Boron in Processing of Carnotite Concentrate

Date: March 13, 1947
Creator: O'Connors, R. J.
Description: It was desired to determine the distribution of boron in the various steps of the processing of domestic ore concentrates containing high percentages of boron. The experiments described in this report were directed toward that end. Summary of this report are: (1) a black oxide containing 0.6 ppm of boron was prepared from material containing 350 ppm; (2) less than 0.02% of the boron in the original material appeared in the black oxide; (3) the iron step did not remove appreciable amounts of boron; (4) the bulk of the extracted boron was removed in the soda salt precipitation; and (5) some of the boron was removed in the acid leach and calcination steps.
Contributing Partner: UNT Libraries Government Documents Department
The Distribution of Impurities in the Ether Extraction Process

The Distribution of Impurities in the Ether Extraction Process

Date: January 22, 1947
Creator: Brimm, E. O., Dr. & Mohr, P
Description: When uranium is purified by the ether extraction method, black oxide is dissolved in nitric acid and ether is added; an ether layer containing uranium and an aqueous layer containing uranium and impurities are obtained. The distribution of some impurities between the two phases and the effect of such impurities on the extraction process were studied. the processing required in the preparation of pure uranyl nitrate might be decreased if, instead of uranosic oxide, sodium diuranate was used as a source of uranium. If it is assumed that uranosic oxide contains the same amounts of impurities as sodium diuranate, with the exception of soda, the extraction of soda by the wash of an ether solution of nitrate prepared from diuranate would be the criterion of suitability of sodium diuranate. The distribution and effect of sodium in the extraction process was therefore investigated, and the results are described in this report. For various of the impurities, the distribution in the process and the effect on uranium holdup in the insoluble cake was investigated. Particular attention was given to the behavior of boron, vanadium, chromium, and molybdenum.
Contributing Partner: UNT Libraries Government Documents Department
Extraction of Uranium from Iron Box Sludge

Extraction of Uranium from Iron Box Sludge

Date: March 11, 1947
Creator: O'Connors, R. J.
Description: It was desired to establish the adaptability of iron box sludge, a residue recovered in the initial concentration of domestic ores, as a raw material from the production of high purity U{sub 3}O{sub 8}. This report summarizes the experimental work on the extraction of uranium from iron box sludge and that on the removal of V{sub 2}O{sub 5} and P{sub 2}O{sub 5} from the solutions.
Contributing Partner: UNT Libraries Government Documents Department
Uranium Peroxide

Uranium Peroxide

Date: April 14, 1947
Creator: Brimm, E. O., Dr. & Nohr, P.
Description: It was desired to investigate the precipitation of UO{sub 4} in acid solution, in order to determine the suitability of this reaction for use in the purification of uranium. A series of tests was performed to establish the conditions for precipitation of UO{sub 4}. It was found that uranium could be completely precipitated from pure uranyl sulfate solution at a pH of 2.5 to 3.5, with only silght excess of H{sub 2}O{sub 2}. The presence of sodium sulfate interferred with complete precipitation. It was established that vanadium was preferentially oxidized, when present.
Contributing Partner: UNT Libraries Government Documents Department
Precipitation of Sodium Diuranate from Pitchblende Liquors

Precipitation of Sodium Diuranate from Pitchblende Liquors

Date: February 4, 1947
Creator: Brimm, E. O., Dr.
Description: In the treatment of carnotite concentrates, sodium diuranate was prepared by acidifying tricarbonate liquors to eliminate carbon dioxide, and then precipitating the sodium salt by the addition of caustic. Direct precipitation of uranium by the addition of caustic to tricarbonate liquors was used when pitchblende ores were processed, because this procedure was more effective in giving a product with a low molybdenum content. Tests of this method in the laboratory and Pilot Plant indicated that low uranium losses (0.2 to 0.3%) would be encountered with typical liquors if 1.7 to 2.0 lbs of caustic were added for every pound of uranosic oxide in solution. Since losses as high as 3% were incurred in plant operations, further work was undertaken, in an effort to reduce the uranium concentration in the waste liquors.
Contributing Partner: UNT Libraries Government Documents Department
Preparation and use of Ammonium Diuranate in the Ether Extraction Process

Preparation and use of Ammonium Diuranate in the Ether Extraction Process

Date: February 4, 1947
Creator: Brimm, E. O., Dr. & Mohr, P.
Description: In the ether extraction process, as originally developed, purified uranium dioxide was obtained by evaporation and calcination of the uranyl nitrate solution, followed by calcination of the resultant UO{sub 3}. It was suggested that an alternate procedure might be developed, involving the precipitation of uranium from the nitrate solution as ammonium diuranate. This material could then be calcined to uranosic acid, or reduced directly to the dioxide. It had already been established that ammonium diuranate could be precipitated completely from uranyl nitrate solutions. Experiments were carried out to determine whether a basic nitrate, analogous to a known sulfate salt, would be formed in the process. Both direct reduction of the diuranate to UO{sub 2} and calcination to uranosic acid were investigated to determine the physical characteristics and residual nitrogen of the resultant brown oxide.
Contributing Partner: UNT Libraries Government Documents Department
Model 411 Scaler

Model 411 Scaler

Date: 1947
Creator: Sewell, C.
Description: Technical drawing of counters and circuits for use in nuclear reactors.
Contributing Partner: UNT Libraries Government Documents Department
Wilson 4" Pump Valve

Wilson 4" Pump Valve

Date: 1947
Creator: U.S. Atomic Energy Commission
Description: Declassified Manhattan Project technical drawings of pumping machinery in nuclear reactors.
Contributing Partner: UNT Libraries Government Documents Department
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