Progress report documenting data collection related to the amount of silt carried by Texas streams and potential effects on water management infrastructure, with an explanation of methods, data broken down by various criteria, and analysis.

In a manner somewhat analogue to that employed by R. Margulies in his memo (BNL Log No. C-2985) on fast source corrections in sigma piles, corrections to be applied to the data obtained on the laid-up graphite in the BNL reactor have been calculated. The correction was computed for a Ra-Be source using the data of Seren and using a standard graphite density for the BNL pile of 1.69. Values of the correction for different experimental sets of data were computed for each of three different diffusion lengths measured parallel to the channels. A correction for diffusion lengths perpendicular to the channels was also determined.

The flux standard is a device which will give a known flux-linkage change to be used as a calibration. At the Radiation Laboratory, two types of flux standards are used, a stationary type and a portable type.

None

The pile physics group reports on reactivity power coefficients from the production test No. 105-248-P, the water leak in B pile, graphite properties, xenon equations from the B pile shutdown of March 1946, and reactivity balance. The experimental physics group headed by J.M. West reports on graphite testing, the P-11 project, and shielding. The experimental physics group headed by E.B. Montgomery reports on diffusion length measurements in the DR and H piles. (GHH)

The redox and pile operations are reported on. Construction in 100 (Pile), 200 (Separation), and 300 (Metal Fabrication) areas is described. General work in the Richland commercial areas and on the Southern Railroad connection is also described. Personnel information is disclosed.

The available information on the ionic and radiochemical composition of current and aged bismuth phosphate process wastes is tabulated here for the convenience of those concerned with metal recovery. In addition to its application in the design of research and development experiments, the compilation may serve to suggest specific needs for additional analytical data. For convenience in chemical calculation, molar compositions have been calculated for the ionic constituents based on the g/1 values usually reported. The dates of radiochemical analyses required for decay calculations should be available from the Analytical Sections at ORNL and HW.

On June 29th and July 13th, 1949, the Industrial Hygiene Group of the Health Instrument Divisions at HAPO conducted a study of the health aspects of the degreaser operations carried on in the Airlock adjoining the 105 Building in the 100 H Area. This was done at the request of the Medical Division. The results of the study, together with certain pertinent information concerning degreaser operation, are reported in this report.

The progress report discusses activities of the P Division for the month of July, 1949. The B and F piles operated at 275 megawatts and the D pile at 305 megawatts throughout the month except for outages listed under Area Activities. A total of 57.5 tons of metal, at an average concentration of 363 megawatt days/ton (MWD/ton) was discharged from the piles during the month. This included 41.9 tons of Class V (alpha-rolled, triple-dipped, completely transformed) metal at an average concentration of 397 MWD/ton which was discharged without difficulty. A portion of this material was inspected and appears to be satisfactory for exposures at this concentration.

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A report which summarizes the performance data obtained from Redox solvent extraction IC Column studies made prior to January 15, 1949 in accordance with conditions of the A.N.L. June 1, 1948, Flowsheet.

Report discussing tests of a new colorimetric method. From abstract: "A colorimetric method, which is a modification of the classical phosphomolybdic acid method, has been developed for the determination of phosphate in synthetic uranium waste solutions...The chief advantage of the method, over those presently included in HW Manuals, is the rapidity with which determinations may be carried out."

A report discussing an experiment conducted to determine the effect of radiation on the melting point of Tempilaq, a commercially available, temperature-indicating liquid.

Abstract: "Small amounts of acetic acid, equivalent to 400 ul. of 0.3 to 0.13 g/L. can be titrated coulonatrically in the presence of a 10 to 25-fold excess of HN03 in 70%, isopropanol. An accuracy of +/- 0.1% and a precision of +/- 8.5% (99% limite) are obtained.

The following document presents designs and blueprints to the bubble-cap column built to replace a nitric acid concentrator.

From introduction: "The present report covers the results of an extended investigation of magnesium oxychloride cements and concretes. In this study the effects of the composition of the cement or concrete on its physical and mechanical properties were determined. In addition, the stability of the mixes was observed."

From summary: "A method for the preparation of normal uranyl carbonate has been developed. Heretofore, this compound has been known only as a rare, naturally occurring material." The report further discusses the physical properties of the compound, its solubility in water, and its interaction with sodium carbonate.

This report for the month of July, 1949 discusses progress regarding work on the carbonate process and the recovery of uranium and vanadium from carbonate liquors.

Report discussing progress made by the National Research Corporation in developing preparation methods for ductile zirconium for the month of July, 1949.

Report discussing a study with the following objectives: "to synthesize pure specimens of both methylisoproplydiketone and 1,1 dinitroisobutane, to determine their physical and chemical properties, and to devise analytical methods which permit their quantitative determination in hexone-nitric acid systems to be encountered in the Redox Process."

Report discussing a geological study for which the objective was to determine the age of Colorado Plateau carnotite. "In addition to quantitative analyses of uranium and lead, the radium-uranium equilibrium of each sample was studied."

Report discussing a study in which "thorium nitrate is quantitatively extracted by mesityl oxide from solutions saturated with aluminum nitrate even in the presence of relatively large amounts of phosphate."

Report discussing a study of 1,000 Gamma-ray logs of oil wells in the central part of the United States which confirmed the use of these logs for the detection of radioactive deposits.

Report discussing a geological experiment in which drill holes in carnotite deposits were logged with the objective of developing a technique for the stratigraphic correlation of ore-bearing beds.