From abstract: "A scintillation detector has a pulse height output which is a linear function of the energy of impinging gamma radiation. A pulse height analyzer system determines the amplitude distribution of this train of pulses. The system also displays this information graphically in a form which is convenient for further analysis."

From abstract: "This report describes a functional mercury vapor detector which is a portable, self-contained, survey instrument, and had a minimum range from zero to two-tenths milligram of mercury per cubic meter of air."

From introduction: "This investigation was undertaken with the general objective of determining whether uranium core could be sheathed with aluminum by an extrusion-cladding process. The ultimate objective of this work was to determine the feasibility of extrusion cladding flat plates of uranium."

From purpose of report: The primary purpose of this report and its appendices is to transmit to the AEC the principal results of the experimental and engineering work done on the low-temperature process and to describe the factors which led to the designs finally adopted.

Report discussing experiments on the interaction of neutron-absorber materials and metal matrix materials used in the fabrication of control rods, such as "boron, cadmium, and some of the rare-earth elements such as gadolinium and europium...In order to evaluate the reactions that might occur during fabrication and use, experiments were carried out in which combinations of the various control materials were heated in intimate contact with the several matrices at elevated temperatures."

Report on the principle of measuring the time-of-flight of neutrons, magnetic-core storage of detector pulses, how pulses are stored, current generator, storage cycle generator, and cathode ray oscillograph.

From abstract: "The stability of polystyrene and phenolic ion-exchange resins to radiation from a Co60 source and from absorbed Ce144-PR144 was investigated. Sulfonated polystyrene cation-exchange resins lost 10 to 20% of their capacity per watt-hour of radiation absorbed per gram of oven-dry resin, while the quaternary amine anion-exchange polystyrene resins lost about 40%. Phenolic cation-exchange resins lost only 1%."

From abstract: "On the 86-inch cyclotron a 41-kw beam has been calorimetered at a net ion loading efficiency of 40%; the average proton current was 1.85 ma at 22.5 Mev. Practical specific yields have been determined for (p,2n) reactions on zinc and bismuth. The investigation of products of proton-induced fission of uranium has been continued and new techniques are being used in measuring angular distribution of reaction products. The 63-inch heavy particle cyclotron is now in operation; N+++ particles have been accelerated to ~25 Mev. In preliminary tests, induced activities have been detected in carbon, nitrogen, and oxygen targets. A hot-cathode ion source is ready for test operation. The 22-inch cyclotron is being used in an investigation of the problems associated with the use of rf and dc electrodes for the acceleration of protons from the ion source into the dees. Radiation-induced corrosion in Inconel tubing containing #21 eutectic (ANP) has been produced by proton irradiation in the 86-inch cylclotron; it is shown that the corrosion was not due to thermal effects. Approximately 150 grams of highly purified U 238 (< 5 ppm U 235) have been prepared, and two grams of thorium 230 (ionium) has been enriched to 90.6%."

Technical report presenting preliminary results obtained in the static corrosion test program to screen promising construction materials for a proposed liquid fuel power breeder reactor.

Technical report describing the downtime of the Brookhaven National Laboratory nuclear reactor and changes made to the reactor facility in March 1952.

From abstract: "This report summarizes the corrosion data obtained for nine construction materials located throughout the ORNL Purex Pilot Plant Acid Recovery Unit during seven hundred hours of operation."

Technical report outlining the determination of the effective resonance integral for U238 as a function of the mass ratio for cylinders of 5/8" to 3" diameter. Also gives a linear approximation of the effective resonance integral with infinite shielding in the form of a function. [From Abstract]

Technical report presenting a summary of the flowsheets, equipment, and progress for the Oak Ridge National Laboratory (ORNL) pilot plant development of the Purex Process and of the ORNL Metal Recovery Program. As of this report, conversion of the Purex pilot plant equipment in Buildings 3019 and 3503 is 90% complete. The building structure for the ORNL Waste Metal Recovery plant had been completed, and 15% of the process equipment had been installed. The first hot runs for this plant were scheduled for June, 1951. [From Abstract; Introduction]

Technical report outlining how uranium hexaflouride was prepared be the direct combination of irradiated uranium metal with elemental fluorine and subsequently decontaminated by adsorption, filtration, and sublimation on a laboratory scale. Report proposes a survey of other methods of preparing UF6 from uranium metal, a study of adsorption techniques for removing plutonium from UF6, and an investigation of fractional distillation for removing the volatile fission product fluorides from UF6. [From Abstract, Summary]

From abstract: "A full-scale, always-safe, metal dissolver for Experimental Breeder Reactor fuel was designed, built, and installed for test operation. It was found that the dissolver operated satisfactorily, and feasible operating procedures were established for the dissolution of bare, or jacketed, EBR slugs. Minor modifications of the dissolver design have been required to accomodate [sic] a modified EBR slug, but it is believed that this will not significantly affect its operating characteristics."

Abstract: "The possibility of transient temperature variations during the self-heating of a plasma by thermonuclear reactions was investigated. Calculations were performed on an IBM Card Program Calculator. Estimates of the time scale for self-heating were obtained. It was concluded that it would be unsafe to assume that the nuclear temperature is always equal to or greater than the electron temperature in a discussion of plasma instabilities for a plasma with 10 percent or greater tritium concentration."

Abstract: "Two parallel wires close together with an arc between them form a hairpin-type of current configuration which should magnetically propel the plasma of the arc. By the time-of-flight measurements with probes it has been demonstrated that directed translational energies of 290 ev can be imparted to deuterons in a plasma produced by a high-current pulsed arc at the tips of two titanium wires loaded with deuterium. It is believed that three deuterons are actually magnetically propelled."

Abstract: This proposal describes a parallel-plate capacitor and the discharge tube with which it is hoped that implosion energies of 1000 eV can be given to deuterons by the pinch effect. The discharge tube is to be arranged so that no external series switch is required.

Abstract: "The deuterium plasma which is ejected by a 6000-ampere pulsed current through a rail-type spark source has a yield in the forward direction which is a factor of 5 to 10 greater than that in the perpendicular direction. This effect is believed to be due to the magnetic propulsion of the plasma."

Abstract: An investigation of ionization by shock waves in hydrogen has been initiated. The shock waves are produced in a 1-inch diameter glass pipe by a high-voltage spark at one end. Variables which will influence attainment of the maximum degree of ionization and ion temperature are described. Spectroscopic methods of measuring ion density and temperature are outlined, and improvements in the design of the shock tube are discussed.

Abstract: Mine mapping of the tyuyamunite-type deposits In the Salt Wash member of the Jurassic Morrison formation of the Lukachukai Mountains, Apache County, Arizona revealed recognizable spatial relationships between ore mineralization and: fractured areas, sedimentary features, and interstitial carbonate.

From introduction: During the summer of 1951, Navajos conducted John W. Chester, Russell C. Cutter, and E. V. Reinhardt, Grand Junction Exploration Branch, U. S. Atomic Energy Commission, to a copper deposit in Copper Canyon. Little radioactivity was noted, and no further work was done in the area at that time. In October 1951, the same group of Navajos reported the discovery of uranium ore in another portion of the same area. The site was visited by Cutter who noted that an excavation made by the Navajos had disclosed a 3-foot thickness of low-grade uranium ore. In November 1951, Cutter again visited the area and observed that the Navajos had opened a 5-foot face of good ore.

Preface: The Fuel Elements Conference held in Paris, France, November 18 to 23, 1957, under the joint sponsorship of the U.S. Atomic Energy Commission and the French Commissarat à l'Energie Atomique (CEA), provided an intensive review of fuel-element fabrication practices and behavior of fuel elements under in-pile irradiation and when subjected to corrosive media.

Introduction: During the winter of 1951-52 the Bureau of Mines, upon the recommendation of the Geological Survey, conducted a churn drill exploration program on monazite placer deposits in the flood plains of several streams in Cleveland and Rutherford Counties in southwestern North Carolina.