Investigatlon of interdiffusion in the aluminumuranium system and of the effects of applied pressure on such systems was about completed. The growth kinetics of the UAl/sub 3/ phase were determined at 400 to 600 C and at pressures of 1 1/4, 5, and 10 tsi. The origin of the macroscopic defects occurring in the UAl/sub 3/ layer during interdiffusion was clarified. The solubility range of UAl/sub 3/ was determined by a nuclear track emulsion technique to be about 2.6 at.% uranium. Exploratory runs were made with incremental diffusion couples of aluminum vs. UAl/sub 3/ and of UAl/sub 3/ vs. uranium disks to determine the growth rates of the UAl/sub 4/ and UAl/sub 2/ phases. A theoretical estimate was made of the importance of pressure-induced shifts in equilibrium concentrations in intermetallic layer growth in the aluminum-uranium and aluminum-nickel systems. (For preceding period see SEP- 251.) (auth)

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In conjunction with Gas-Cooled Reactor heat-transfer studies, local and mean heat-transfer factors are predicted from the heat transfer-mass transfer analogy using subliming naphthalene in air. Experimentation was conducted on 1-in.-dis septafoil rods in a 4-in. -dis flow channel with rod center-to center spacings of 1.10, 1.25, and 1.40 in. at a Reynolds modulus of approximately 60,000. Ratios of local mass transfer to mean mass transfer for a given rod vary as much as from 0.7 to 1.3 (outer rod, 1.10-in. spacings). Mean values of the mass-transfer factor are, in general, above that predicted by the correlation j-0.023 NRe^-0.2; as much as 46% got the outer rod t 1.25-in. spacing. The data indicate that for maximum mass transfer and minimum variation of the mass-transfer factor, an optimum rod spacing exists; the best observes is at 1.40-in.

A critical review of the methods reported in the literature for the study of gas-metal reactions in high and ultra-high vacuum systems is given. Experimental apparatus and techniques based on volumetric, gravimetric, magnetic, and other properties of the metals including work function, accommodation coefficient, resistivity, and others have been used. A volumetric method, based on a determination of rate-of-reaction, was selected as most readily applicable to the proposed investigation. (auth)

The following report describes the workings and development of the nuclear ramjet propulsion systems.

Since the inauguration of the Off-Site Animal Investigation project n 1957, there has been one annual report rendered as of 30 June 1958. this is the second annual report dated as of 30 June 1959. The objectives of the project have been unchanged during the past year. These are (1) to enhance the Nevada Test Site/off-site rancher relationship through an active investigation project in their interests, and (2) to provide further information as to the status of the off-site animals in their environment, with special emphasis on their radioactive isotope uptake from fall-out. isotope uptake of the animals is being emphasized as well as the gross and microscopic histopathological examinations. Two year's existence in an area of radio-contamination where a full fission spectrum of isotopes can be found, where radiation background reading range from 1/2 mr per hour to 1 = per hour, has produced no noticeable effect on the animals.

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At the request of Hanford Operations Office, Atomic Energy Commission, a study was made of the effects on the Hanford Facilities of a navigation and power dam at Columbia River mile 348, about five miles upstream of the 300 Area. The original study was based on a nominal slack-water pool elevation of 395 to 400 feet at the dam location. A supplemental study evaluated the effects on plant facilities of a dam at the same location but with slack-water pool elevation of 385 feet. In addition to effects of the dam on Hanford, a study was performed to evaluate the effects the dam would have on the environment.

Abstract: Fission product measurements were made on the SM-1 primary coolant. The airborne activity observed during the sampling of the primary system was identified. An analysis was made on the primary coolant for alpha activity and on the secondary water for fission production iodine.

Physics experiments were performed on the SM-1 core. Measurements were made on five rod bank positions and rod calibrations. The reactivity effects of core modifications were investigated. Modifications to the core included replacement of the boron absorbers in rods 1, 2, 3, 4 and C with europium absorbers; replacement of a control rod fuel element with one containing an integral europium flux suppressor; and replacement of a stationary fuel element. Additional experiments were designed to determine the reactivity of the SM-1 with 4 and 8 stationary elements removed; the neutron flux in the biological shield and in the region of an integrai europlum flux suppressor; and the gamma flux above the core and from irradiated control rod components. (auth)

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Authority of county tax collector as to issuance of poll tax receipts and exemption certificates in affidavit form.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Validity of the portion of the Willis Avery grant not specifically covered by court decree.

Either system appears to be fairly satisfactory from a containment standpoint. Current results indicate probable over-all rates of about 0.2mils/mo for titanium vs. 1.5-3.0 mils/mo for Ni-o-nel. Tests are not 100% comparable due to changes made in flowsheet conditions, but have been of sufficient variation and length as to allow good predictions to be made. Both metals show some tendency toward local attack in Thorex solutions. These tendencies are increased by poor welding techniques.

For several years, a major category of fuel element failures has been the side corrosion type, characterized by localized accelerated fuel element jacket corrosion. Since it has been demonstrated {sup 1} that misalignment of fuel elements in a process tube will produce flow patterns and accelerated corrosion, termed ``hot spots``, failure to align the fuel elements in process tubes is considered a contributing factor in the production of side corrosion failures. Preliminary testing of both self-supporting and ``bumper`` fuel elements is underway. Data on the self-supporting fuel elements have demonstrated that the bridge-rail projections have sufficient support strength, do not of themselves create a corrosion problem and in actuality probably eliminate any hot-spot areas. Although one tube of bumper fuel elements in KW Reactor {sup 3} has been discharged, data are not as yet available. Potentially, the most sever corrosion conditions exist during the summer months when reactor inlet temperatures are high. It is desirable then, provided bumper fuel elements limit hot- spot corrosion, to evaluate the bumper concept for large scale use possibly by the summer of 1960. To accomplish this, a demonstration loading of the bumper type fuel elements must be underway by about July, 1959. The purpose …

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Questions relating to what items are court costs and payable as such by the State under the provisions of Article 3912e, V.C.S.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Whether the policy followed by the Texas Education Agency and the method employed in filing expense claims where a group return is involved is in accordance with the legislative intent set out in the current General Appropriation Act.

The material covered are R and D, 2000 reactor and metallurgy program (production reactors, N-Reactor). Topics covered include operating schedules and production, fuel, engineering, safety, control, physics, etc.

Equilibrium loading of uranium on Dowex 21K was studied in a sulfate system for uranium concentrations from 0.0005 to 0.005M, total sulfate concentrations of 0.045 to 0.6M, and sulfuric acid concentration of 0.020M. Loading data were fitted to Langmuir adsorption isotherms and Langmuir constants were evaluated. Resin was equilibrated with uranium feed solutions by flowing the feed through a shallow fixed bed of resin. (auth)

Equilibrium loading of uranium on Dowex 21K has been studied in a sulfate system for uranium concentrations from 0.0005 M to 0.0005 M, total sulfate concentrations of 0.45 M to 0.6M, and sulfuric acid concentration of 0.020 M. Loading data have been fitted to Langmuir adsorption isotherms and Langmuir constants have been evaluated. Resin was equilibrated with uranium feed solutions by flowing the feed through a shallow fixed bed of resin.

In a preliminary experiment, the integral diffusivity of 1 M FeCl/sub 3/ solution varied uniformly with the fraction difiused: from 0.3 x 10/sup -6/ cm/ sup 2//sec for 10 per cent diffused to 0.8 x 10/sup -6/ for 30 per cent diffused. A short Fluorox run made with crude UF/sub 4/ in the 4-in. fluidized bed showed that UF/sub 6/ could be produced from the impure feed. Denitration of Th(NO/sub 3/)/sub 4/ solutions on fluidized or mechanically agitated beds of ThO/sub 2/ and gave fine ThO/sub 2/ particles for all conditions tested. The rate of sorption of uranium into 40 micron Dowex 21K resin particles from a 0.0042 M uranyl sulfate solution was studied by measuring the uranium loading on individual beads as a function of time. Chloride concentrations of 28 to 51 ppm were produced in the solvent extraction feeds during five feed adjustment runs made with the Darex Reference flowsheet. Decladding of SS-clad /sub 4/ gave essentially identical results as batch decladding. When a Mark I prototype assembly was sheared into 0.75-in. lengths with a"plane of contact" blade in the 126-ton Manco shear, 22.2 g of metal fines (304L stainless steel) 1680 microns or less in size was …

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A test program conducted to develop high integrity piping and seal components for Plutonium Recycle Test Reactor installation. Methods of preventing leakage of costly D2O coolant and maintaining operational safety were investigated.

Report documenting ongoing experiments, designs, and tests undertaken by the Oak Ridge National Laboratory for the Molten-Salt Reactor Project.

In compliance with a request from Coolant Testing Operation, the Reactor Engineering Operation has made a study to determine the maximum operating pressure limits for the pertinent Zircaloy-2 process tubes. Since these tubes shall be used for testing NPR fuel elements, it is considered desirable that KER Loops 2 and 3 permit operation at temperatures of around 300{degrees}C while the NPR prototype facility permit operation at about 316{degrees}C in a manner such that there is minimum hazard to the KE-Reactor and to personnel.