This progress report discusses the work during the fourth quarter of 1951. During this quarter, "the uranium raw materials program at ORNL has been devoted to studies of uranium chemistry and to the development of processes for deriving uranium and byproducts from various types of ores" (From introduction).

From introduction: "During the second quarter of fiscal year 1952, the Isotope Production and Process Development Department placed primary emphasis on the collection of lithium, iron and calcium isotopes."

From summary: "During 1951 NDA has, at the request of ORNL, been studying the supercritical-water reactor as proposed for aircraft propulsion in Wash-24...This study has concerned itself only with the reactor and shield." The report describes the reactor and the processes involved in developing it. The goal of the development of this reactor is identified as a path to supersonic flight.

From abstract: "The reaction between hydrogen and oxygen with the aid of various catalysts (especially platinum on aluminua) has been studied, and the operating variables such as flow rates, space velocity, temperature, and gas composition have been examined rather extensively. It has been found that hydrogen and oxygen in stoichiometric proportions and mixed with either steam or helium may be made to react to the extent of 99.5% or greater at space velocities up to 30,000 hr-1, or even higher, at temperatures from 100[degrees] to 900[degrees]C, and with mixtures ranging from less than 1% hydrogen to mixtures containing 12% hydrogen and 6% oxygen. Richer mixtures, including undiluted electrolytic gas (H2 + 1/2 O2) have been used with catalysts less active than platinum (e.g. copper, silver, nickel and V2O5) but here the gas mixture is explosive and care must be taken to prevent explosions. The thermal reaction between hydrogen and oxygen diluted with steam has also been investigated at temperatures between 500[degrees] and 800[degrees]C."

Technical reports outlining the controls for the Homogeneous Reactor Experiment (HRE); controls are divided into three principal groups. 1. Reactor. 2. Process or auxiliary. 3. Power generation. These are the classifications designating the primary functions of the controls. [From Introduction]

The first part of this quarterly progress report details reactor theory and design, discussing the aircraft reactor experiment, experimental reactor engineering, reactor physics, and critical experiments. The second part of this report is not included. The third part of this quarterly progress report details materials research, discussing corrosion research, physical properties and heat-transfer research, metallurgy and ceramics, chemistry of high-temperature liquids, and radiation damage. The fourth part of this quarterly progress report details alternate systems, discussing a supercritical water reactor, circulating-moderator-coolant reactors. The fifth part of this quarterly progress report includes appendixes.

From to the files: The Shinarump-Moenkopi contact on Oljetoh Mesa in the Monument Valley district, Arizona-Utah, was examined from November 5 to 15, 1951, to determine the location of and the mineralization in Shinarump channels. Twenty-seven distinct channel outcrops were located and examined. Three of these channel outcrops are mineralized and the remaining 24 are barren. Plate I shows the distribution of the Shinarump, the Moenkopi, and the DeChelly member of the Cutler formation; the location of the Shinarmp channel outcrops; the channel trend where there is good evidence for such a trend. The Hoskinrnini tongue of the Cutler was mapped with the Moenkopi as it is not a good mappable unit in this area. The three mineralized outcrops are indicated by the letters A, G, and AA while the barren outcrops bear the letters B to F and H to Z.

Technical report presenting the results of a study of the AEC thorium production facilities at Iowa State College, Ames, Iowa. Operating procedures, descriptions of equipment and a production cost analysis have been included in this study.

The following report provides measurements of the crystalline structure of neptunium metal.

The following document is meant to inform the reader on the makings of a cement base for the hot filament mass spectrometer source as part of a publication in the review of scientific instruments, "Laboratory and Shop Notes".

This report follows a study that was undertaken to evaluate the practicality if removing the heat from the reactor cooling water by means of a "flash cooler" and to compare its economics with that of the conventional heat exchange system.

"This report covers mainly the work completed since the last interim report, HNL Log No. 0-4714. This report includes results from studies of the rare earth distribution in bismuth-uranium and fused chloride and studies of fused chloride behavior."

Report discussing the fractionation study of tri-n-butyl orthophosphate as the organic phase using a solution of trivalent rare earth chlorides or nitrates as the aqueous phase.

From introduction: "A simplified calculation has been carried out in order to gain some insight into the flux distribution, peak to average power density, efficiency of a catching blanket and the effect of a reflector in the proposed converter reactor."

Introduction: "This letter is intended to provide a brief summary of the information presently available on the engineering properties of iron-linonite concrete with the view of adapting such concrete with the view of adapting such concrete for use as biological shielding material in a Hanford pile. By reducing materials and fabrication costs, such a adaptation might effect a savings of at least two million dollars per pile over the present iron-masonite laminated shield structure."

Monthly report of the U.S. Geological Survey's trace element investigations including an outline of field work, laboratory work, and staff activities that have been completed or are in process.

Discussing and investigation with the purpose of examining a uranium prospect which was reported to be in active development

Quarterly summary report of studies conducted through the Radiation Laboratory, University of California. Some results reported in the report may be of a preliminary or incomplete nature.

This technical report presents "a theoretical study of the motion of gas bubbles in a rotating liquid" in order to "make comparison with experimental data from an investigation concerning the removal of gas bubbles from rotating liquids as descriped in ORNL-630." The report presents a literature review of "motion of gas bubbles in liquids" and provides a "summary of extensive experimental studies at the University of Tennessee." It also presents "an expression for the radial velocity of a gas bubble in a rotating liquid based on principles of mechanics." Finally, this report presents "a method for computing the steady state state [sic] gas hold-up in the HRE reactor core under power producing conditions." (From introduction)

From abstract: "Operation of the 86-inch cyclotron has been continuous except for a three-day interruption caused by a water leak inside the vacuum chamber; monthly output has averaged over 210,000 [mu]a-hr; the average continuous (168-hour week) beam power has been approximately 5.5 kw; and the energy of the beam has been determined to be ~19.4 Mev. No changes due to radiation damage have been detected in Inconel tubes containing UF4-NaF-KF eutectic which were irradited in the 96-inch cyclotron with power inputs up to ~415 watts/cc. The major components of the 63-inch cyclotron have been fabricated and are being tested as the machine is being assembled. On the 22-inch cyclotron a radius-wise examination of the fine structure of the proton beam reveals definite proton orbits. Several grams of very pure uranium 235 have been prepared; the chemical recovery for first-stage separation of U 236 has been established as 97%; and facilities for laboratory-scale separation of plutonium isotopes are being prepared."

Report issued by the Brookhaven National Laboratory discussing the instrumentation, operation, and maintenance of the established area radiation monitoring stations. This report includes maps, tables, illustrations, and photographs.

This technical report presents the process design for the thorium semi-works plant which will be located at the Feed Materials Production Center, Fernald, Ohio. It contains the process information required for the layout and detailed mechanical design of the thorium plant.

Discussing a study of the alteration effects may furnish information concerning the fluids emanating from the magma which gave rise to these now defunct and much eroded roots of a hot springs area.

Discussing an examination made of Green Vein Mesa in the southwestern part o he San Rafael Swell in Utah to determine the extent of uranium mineralization.