The chemical potential of the brine from I.I.D. Well No. 1 was evaluated and reported in Rogers Engineering Coo, Inc. March 1962 Flow Test Report. This evaluation considered only the recovery of sodium chloride, as the prime salable product and alternately as the raw material for conversion to salable chlorine and caustic. Both cases showed low net revenue relative to the estimated capital investment required. The subsequent three month well flow test indicates continued production of a consistent type brine can be expected from this well. Based on the flow and composition data established during this test period, chemical production potential has been examined. The separation and sale of high quality potassium chloride appears attractive. Attached are sketches of each of the two production schemes considered with estimates of capital and operating costs and revenue.

It is the purpose of this document to provide the scope of piping changes that are needed to supply gravity-fed water to the reactor storage basins on an unattended basis following complete reactor discharge of metal into these basins.

The KER loops are four pressurized water-cooled in-reactor testing loops in which fuel, coolant and corrosion tests are being conducted for the N Reactor program. Two of the loops, KER-3 and KER-4, are equipped with N-size Zr-2 process tubes and have sufficient pumping and heat dissipation capacity to permit testing of 14-element charges of N fuel. The other two loops, HER-1 and KER-2, are fitted with Zr-2 process tubes of 2.1 in. inner diameter (vs 2.7 in. for N). The small loops can be used to test charges of N inner tubes or other elements sized at about 1.8 in. outer diameter or less. An inert sleeve must be used with N inner tubes to assure adequate coolant flow over both surfaces of the elements. The KE reactor active zone is 28 in. long com pared to 35 in. for N so the length of test charges is somewhat shorter than actual N charges will be. The purpose of this report is to review the testing environment, to discuss the testing program and to present the schedule as presently seen.

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, Waggoner Carr, regarding a legal question submitted for clarification: Constitutionality of Senate Bill No. 212

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, Waggoner Carr, regarding a legal question submitted for clarification: Under the submitted facts, whether the Gross Receipts Tax provided for by Article 11.03, Taxation-General, is due by the stated corporations.

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, Waggoner Carr, regarding a legal question submitted for clarification: Whether the Texas State Board of Medical Examiners is authorized to issue a license in Texas as a medical doctor, to a graduate from an osteopathic school in California, who elected under California law to use the suffix “M.D.” instead of the suffix “D.O.” under the stated facts.

The objectives of this production test are: 1. To authorize the outage time involved in installing and removing oxidation monitors for the reactors, and 2. To specifically define sample design, spacing of samples in the channels, and residence times to insure adequate routine monitoring of moderator oxidation rates. This production test is concerned with B, C, D, F, DR, F, and H reactors. Similar requirements have been specified in PITA IP-20-I for KE and KW reactors

Monthly newsletter from Dallas, Texas published by the Stamps Quartet Music Company that includes news and information concerning gospel music along with advertising.

Daily newspaper from Cuero, Texas that includes local, state and national news along with advertising.

Faculty bulletin letter from the Office of the Dean of McMurry College, granting excused absence for the school's chanters (listed alphabetically and by gender) who were on tour April 1-5.

Daily newspaper from Sulphur Springs, Texas that includes local, state, and national news along with advertising.

Hydraulic and deflection analyses of the unequal flow passages in the HFIR control region revealed excessive pressure differentials. A proposal to drill connecting holes between the flow passages initiated an experimental program for investigating the effectiveness crossflow on pressure equalization. Empirical constants for an analytical model and experimental design data on reduction of pressure differentials between channels were obtained. It was determined that crossflow between channels would satisfactorily reduce the pressure differentials. (auth)

The pre-Buggy experiment was designed to measure the fraction of vented radioactivity from a series of HE underground detonations containing radioactive sources. Capsules containing curie amounts of La/sup 140/ were sufficient to provide a radiotracing of the debris which resulted from the detonation. Particle size measurements of the debris indicated that La/sup 140/ was adsorbed on the surface of the soil particles. Some 96% of the activity was associated with sub-sieve particles representing only 8% of the mass and 90% of the available surface area. (auth)

Metals ---technology of high-temperature liquid, review; Systems for Nuclear Auxiliary Power (SNAP-2) ---coolant boiling research for; Nuclear Power Plants ---development research on thermionic, Los Alamos Molten Plutonium Reactor Experiments ---fuel element analysis; Heat Transfer Systems ---conference on liquid metal; Bearings --coating for liquid metal, performance of; Systems for Nuclear Auxiliary Power (SNAP-8) ---component development; Sodium---heat transfer research on; Mercury --heat transfer research on; Potassium ---heat transfer research on; Nitrogen Systems ---Hg --N, flow characteristics for two-phase; Mercury Systems ---Hg --N, flow characteristics for two-phase; Nuclear Power Plants ---heat transfer rejection by space, research on; Alkali Metals ---heat transfer research on; Turbines ---development of twostage potassium; Bearings --- development of liquid-metal lubricated; Niobium Alloys ---properties for alkali metal containment, research on; Rubidium ---thermophysical properties of; Los Alamos Molten Plutonium Reactor Experiments ---design of LAMPRE-1. (D.C.W.)

The corrections required to deduce unperturbed neutron fluxes from measurements with foil absorbers were determined experimentally for the case of gold foils exposed in a light-water medium. The results are in good agreement with the theoretical predictions of Dalton and Osborn and of Ritchie and Eldridge. (auth)

Activities of the radiation safety program at Oak Ridge National Laboratory for the period 1960-1962 are described. A reduction in the frequency of radiation accidents was observed and a training program for technical and nontechnical personnel has been formulated. Sixteen facilities were improved to ensure safe operation at a cost of approximately 388,589. A comprehensive Radiation Warning and Communication System is being installed in three phases over a period of three years ending in FY 1964. (auth)

The program, TENSOR, for the calculation of underground explosion phenomena and other time dependent problems involving the motion of elastic, plastic, fractured, and fluid materials is discussed. The method used in the code allows treatment of transient phenoraena in two space dimensions (cartesian or axial symmetry), and is particularly appropriate for problems involving compressible flow, large displacements, and free transitions of material between the elastic, cracked, plastic, and fluid states. The equations of motion are a straightforward generalization (to include a stress tensor) of conventional Lagrangian techniques for compressible flow and shock hydrodynamics problems. Methods for defining the stress system are discussed, and examples are included. (auth)

Design and operation of an electronic ripple filter to be used with the Brooknaven alternating-gradient synchrotron during flattop at energies between 10 and 30 Bev are discussed. (D.C.W.)

The effect of irradiation on the hydrolytic behavior of uranium monocarbide as related to the aqueous chemical processing of these reactor fuels is being investigated. The fabrication, evaluation, and encapsulation of the UC in niobium prior to irradiation is described. Uranium monocarbide buttons were prepared by arc-melting 1.51%enriched uranium metal with the stoichiometric quantity of spectroscopic-grade carbon. The buttons were then remelted and drop- cast into graphite thimbles 3/8 in. dia, and 3 in. long. The cylindrical castings were surface ground and cut into 0.17 in.-thick pellets, which were then polished. Preirradiation evaluation included metallography, chemical analysis, and hydrolysis studies. Microstructures of the final pellets indicated that the monocarbide was nearly stoichiometric; however, some alpha -uranium was present along with carbon contamination from the graphite thimbles. The use of tungsten- tipped electrodes in the arc-melting operation introduced about 0.3% of tungsten impurity. The composition of the pellets, as estimated from hydrolysis studies and chemical analyses was 92% UC, 3.5% UC/sub 2/, 4.0% uranium metal, and 0.3% WC. The UC pellets were encapsulated in niobium and subsequently shrunk-fit into a stainless steel cladding. The capsules were sealed by heliarc welding in a helium atmosphere chamber. (auth)

An experimental flight test was made to verify and improve the methods and techniques used to predict the aerothermodynamic effects on re-entering SNAP devices. The amount of aerodynamic heating as a function of body shape, size, and mode of entry was indicated. Test specimens yielded trajectory, aerodynamic heating data, heat distribution, and heat transfer of known bodies. IBM 7090 digital programs were utilized and so constructed that one digital code complemented the other, i.e., at any time during the re-entry period, the complete thermal history of the body is known. The test specimens consisted of lead bodies containing alkali metals, used as flaring material, and a larger titanium cylinder containing telemetry equipment to monitor the exterior and interior wall temperatures during re-entry. By judicious placement of transducer sensors, aerodynamic heating rates and mode of entry, i.e., tumbling, spinning, and/or stabilized, were determined. The lead bodies were consumed at high altitudes whereas the telemetry capsule survived re-entry. (auth)

Progress made during the period is reported including analyses of experiments and tests, and evaluation of effort. The subject material concerns reactor transient and excursion tests, fission product release studies, end-of- life shutdown devices, critical configuration studies, mechanical and thermochemical effects, reactor separation and fuel element ejection, and reentry burnup of fuel elements. The design of the SNAPTRAN 2/10A-1 and -2 machines was essentially completed and fabrication of major components was initiated. The fission product release tests at the NRTS were completed. Some progress was made on the explosive shutdown projectile design. A practical shipping sleeve design was demonstrated which will maintain the SNAP 2/10A assembly in a subcritical condition as a result of postulated shipping accidents. The Phase I ground test series were completed. The computer code, RESTORE, was shown to be excellent for the calculation of reentry trajectories. The calculation of fuel rod heating and ablation using a digital thermal analyzer program resulted in an improved and more elaborate analytical model. (auth)

Thermodynamic considerations indicate that sodium should be favorable for the one-step reduction of UF/sub 6/ to uranium metal. A reaction vessel was developed for the continuous reduction of UF/sub 6/ to metal with batch collection of the products, and several experimental tests established the chemical feasibility of this direct and continuous reduction. Up to 93.5% of the uranium content of UF/sub 6/ continuously reduced by sodium in a reaction vessel was recovered as massive uranium metal in the form of a metal button of acceptable purity. A remaining problem is development of compatible materials of construction. (auth)

The Fuel Cycle Facility for the Second Experimental Breeder Reactor (EBR- II), the process equipment, and the operations to be conducted in the facility are described. The Fuel Cycle Facility is a plant for reprocessing, by pyrometallurgical methods, the core and blanket material discharged from EBR-II. The reactor core alloy is uranium-5% fissium and contains about 46 wt.% U/sup 235/ . The blanket material consists of U in which plutonium is bred. Core and blanket subassemblies contained in transfer coffins are transferred between EBR- II and the Fuel Cycle Facility, which is in an adjacent building. The Fuel Cycle Facility consists primarily of an argon-atmosphere cell where fuel processing is done, an adjacent air-atmosphere cell where reactor subassemblies are assembled and disassembled, and an operating area (for personnel) which surrounds the two cells. Because of the high levels of activity expected, the fuel-handling-and- processing equipment is designed for remote operation. Remote processing is accomplished with the aid of bridge cranes, electromagnetic bridge manipulators, and master-slave manipulators. Transfer ports and air locks are used in the transfer of materials and equipment into the air-atmosphere cell and between the two cells. The walls between the argon-atmosphere and air-atmosphere cells and the operating …

Even though VBWR shutdowns were required for location and removal of five failed fuel assemblies (HPD Program), the increase in fuel exposure was good. Fuel exposures wili pass the values at which cold worked stainless steel cladding was failing under the HPD Program. Failure of the 0.005-inch cold worked stainless steel clad fuel rods in assembly 8L was traced to strain cycling fatigue. A study of tapered fuel rods indicates a potential advantage for us of a variable water/fuel ratio along the flow channel. Natural circulation tests in the hydraulic stability loop were conducted over a range of conditions from stable, to oscillatory with exponential decay, to self-sustaining oscillation of constant amplitude, to unstable oscillations with divergent amplitude. The response to impulses in power input shows the effect of the time delay for transporting steam voids up through the riser. The data permit calculation of oscillation frequency, damping coefficient, time lags, and show the magnitude and character of pressure and velocity changes. The data, which have an experimental scatter of plus or minus 10% maximum, show that burnout heat fiux: decreases with increasing flow up to 2 x 10/sup 8/ lb/hr-ft/sup 2/; has a maximum for hydraulic diameter between 0.25 …