Abstract: "Thorium is separated from uranium, titanium and tungsten by precipitation as fluoride. The precipitate is ignited to oxide, dissolved in nitric acid, evaporated with perchloric acid, neutralized to a pH between 2.0 and 2.5 and titrated with the disodium salt of ethylene-ddiamine tetrascetic acid, using Eriochrome Cyanide as indicator. If less than 30 milligrams of thorium is present, lanthanum is added as a carrier."

From abstract: The response of the reactor to forced oscillations has been investigated with the pile oscillator technique and the data are presently being analyzed.

Report discussing the heating of a plasma which passes through a series of magnetic pumping cells by applying the second-order theory of transit-time heating developed by Berger and Newcomb. From abstract: "Transit-time magnetic pumping in single-transit systems seems to be a feasible method of increasing plasma energy by amounts of the order of a factor of 10."

Progress report discussing projects and work completed by the University of Michigan Department of Chemistry 1957-1958.

This report describes the circumstances leading to the accident, attempts to reconstruct the nuclear reactivity conditions, and reviews the dosimetric means and results which were used to help determine the exposure of affected employees.

Discussing holes drilled in order to evaluate the uranium potential of the Bee area in San Juan County, Utah.

Describes the design criteria, design details, and final installation of a high precision temperature and intimate contact monitor.

Abstract: A drilling program was conducted by the Atomic Energy Commission on Cove Mesa, Arizona to further develop uranium and vanadium ore reserves that are vital to the National Defense. The drilling was performed by the Minerals Engineering Company of Grand Junction, Colorado. Uranium and vanadium ore horizons are found in the Salt Wash member of the Morrison formation on Cove Mesa.

Abstract: From December 1953 to May 1954 an extensive airborne reconnaissance program was conducted in northwestern Arizona (Arizona Strip) and southwestern Utah. Five surface anomalies were detected, one of which has possible commercial value. All anomalies are within the boundaries of National Park Service jurisdiction, consequently, this report is not for public distribution until clearance is obtained from the National Park Service. A preliminary airborne reconnaissance program was also conducted in the Richfield area. No anomalies were discovered.

Investigation to evaluate some of the designs, techniques, and methods for fabrication of a root pass.

The hydrogen contents of several types of fabricated uranium have been determined by a vacuum method and expressed in terms of ccH2/ccU. The data indicate that alpha-rolled metal contains about 0.25 ccH2(STP)/ccU whereas beta heat-treated uranium yielded values between 0.30 and 0.37 cc per cc. Restricted efforts were made to determine where in the heat treatment the 5 to 10 cc of hydrogen per slug were taken up. It appears that no one operation is wholly responsible for this additional gas, although reactions between beta heat treated surfaces containing microscopic defects, and nitric acid may possibly play a large role. In general it may be said that slug produced by powder metallurgical techniques contain less hydrogen than pieces produced by rolling and heat treatment.

Abstract: "The recurrent difficulties experienced in routine operation of the high voltage supplies and main control panels of the standard assay instruments are indicated. New supply and distribution units, which were designed to avoid these difficulties, have been constructed and tested. This report briefly describes these units and presents a more detailed description of a high current power supply and main control panel."

From introduction: This report is a compilation of the presently available data pertaining to the proposed reactor power plant site which may be used in evaluating the proposed measures for protecting the public from possible radioactive hazards, both during normal operation and under unusual hazards.

This report provides the results to an airborne radiometric reconnaissance made in central Montana, the Sweetgrass Hills and Arch area, and Clancy area of the Boulder batholith that was completed in October 1953. This report is divided into three parts, each area is discussed separately according to its geology, the airborne procedures employed, and the conclusions reached.

"Continued progress has been made with the high temperature decontamination processes for irradiated uranium fuel. The fused salt treatment of molten uranium has been extended to UCl3. Plutonium and rare earths were extracted into the UCl3 phase. Direct plutonium distillation from molten irradiated uranium has been scaled up to the hundred gram scale. Solid scavenging experiments using uranium oxide, uranium carbide, and uranium nitride in contact with molten uranium have indicated fission product removal. A scaled-up investigation of the separation and recover of uranium from an SIR type ceramic fuel using the volatile fluoride process has indicated the feasibility of this separation method. The effect of irradiation on the decomposition of BrF3 has been further studies in experiments using the NAA statitron.'

"Scale-up work on high temperature fuel recovery processes has progressed to the point where the (high temperature) vacuum furnace for several operations to the hot cells has been completed and tested under operating conditions. Small scale experiments on high temperature methods for processing molten irradiated uranium fuel have been made with spent X-10 fuel slug pieces. The results of direct Pu evaporation, treatment with fused fluorides and oxide scavenging were every similar to those found with tracer experiments."

"Work has continued on high temperature methods for processing irradiated uranium fuel. Additional results have been obtained with fused halide treatment, solid scavengers and direct Pu distillation. With fussed fluorides about 95 per cent of the Pu was removed from a uranium sample, while treatment of uranium with HC1 gas removed almost all the Pu and many fission products. treatment of molten uranium with uranium oxide removed a substantial fraction of the fission products without removing Pu. Uranium carbide treatment results were similar to the oxide but not as effective. A small scale distillation of Pu from uranium showed that Raoult's law is obeyed."

"The preliminary design of a 3095-Mw(thermal), helium-cooled, graphite- moderated reactor employing sign conditions, 1500 deg F reactor outlet gas would be circulated to eight steam generators to produce 1050 deg F, 1450-psi steam which would be converted to electrical power in eight 157-Mw(electrical) turbine- generators. The over-all efficiency of this nuclear power station is 36.5%. The significant activities released from the unclad graphite-UO₂ fuel appear to be less than 0.2% of those produced and would be equivalent to 0.002 curie/ cm/ sup 3/ in the primary helium circuit. The maintenance problems associated with this contamination level are discussed. A cost analysis indicates that the capital cost of this nuclear station per electrical kilowatt would be around 0, and that the production cost of electrical power would be 7.8 mills/kwhr" (p. iii).

Report containing reports from the Physics Division of the Oak Ridge National Laboratory that cover a wide variety of subjects.

Discussing velocity logging carried out during six weeks of fieldwork in 1955 through contracts with the Texas Company.

Classical polarography and voltammetry with other electrodes are discussed . 189 references taken from literature between mid-1957 and mid-to-late 1959 is surveyed.

A report discussing a diamond drilling project in the Silver Reef District and adjacent areas, with the propose to obtain geologic information as well as to further explore the Chinle formation for new ore bodies.

The design and construction of a 1,000,000 fps rotating mirror frame camera is described. Twenty five consecutive pictures 20 mm in diameter can be obtained on a strip of 35 mm film. A resolution of at least 20 lines/mm is obtained on a moderately fast film like Linagraph Shellburst. Accurate synchronization of the event to be photographed is required. The camera has been most useful in the investigation of explosive and related phenomena.

The purpose of this program is to summarize and evaluate the potential usefulness of in situ tracers, design and construct prototypes of large low-level soft beta counters for industrial application, especially of such isotopes as carbon-14 and tritium, and design and construct a prototype of a large low-level liquid scintillation detector for use vi the process gamma counting.