Report discussing the rolling of thorium rods. Abstract: "Thorium rods, 1-7/16 inch in diameter, were rolled from Ames castings. The billets were roughed down in diamond-grooved rolls and finished in hand-rounding rolls. Remelted chips as well as primary-metal castings were rolled, and both yielded satisfactory rods. The surface quality of the rods was generally excellent, and the machined slugs were free of seams."

Report discussing studies testing various thorium alloys consisting of either Ames thorium and up to 5% of various additions or Ames thorium and up to 50% uranium. Effects of molybdenum additions for fusion welding, and cold-work strengthening were also tested. Methods, experimental data, and discussion is included.

Report discussing the reaction of uranium with pure water. The reaction was followed by using a method of measuring hydrogen evolution.

From introduction: The reconnaissance was made during the summer of 1951 by two field parties: (1) a reconnaissance in parts of Oklahoma, Texas, New Mexico, and Arizona by Russell Gibson, and (2) Geological Survey reconnaissance in parts of New Mexico,.Colorado, Utah, Idaho, and Wyoming (by the writers), the results of which are summarized in this report.

From abstract: Radiometric reconnaissance in several districts of the Alaska Railroad-Iliamna region during 1951 found no radioactive material in excess of 0.002 percent equivalent uranium associated with certain lode deposits that previously were deemed favorable for the occurrence of uranium because they contain mineral assemblages similar to uranium-producing lodes elsewhere.

Abstract: No radioactive material in excess of 0.002 percent equivalent uranium was found during 1951 in a reconnaissance of possibly favorable lode deposits in the Nuka Bay, Moose Pass-Hope, and Girdwood areas of the Gulf of Alaska region.

Abstract: In May 1950, 350 miles of road was traversed in the vicinity of a torbernite locality in New Jersey. The radioactivity of the area traversed was two to three times above normal, averaging 0.003 percent equivalent uranium. It is estimated that there is 1,000 tons of rock averaging 0.009 percent uranium at the torbernite locality. The presence of this area of above-normal radioactivity suggests that further study is needed in the Piedmont belt and the flanking sediments, which may contain economic deposits of uranium minerals.

Technical report outlining measurements of the equilibrium in the exchange of deuterium between ammonia and hydrogen and of the kinetics of this reaction. Details a series of tests carried out to measure Murphree plate efficiencies.

Technical report describing the results of the chemical reaction between potassium amide and liquid ammonia and the exchange of hydrogen between hydrogen gas and liquid ammonia. This report finds that the reactions may be sufficiently rapid to be useful for isotope separations on a larger scale.

Technical report analyzing the down time of the Brookhaven National Laboratory nuclear reactor and resulting changes in reactivity.

Technical report detailing kinetic equations that have been developed for a boiling-type reactor and inherent reactor stability studies that have been made on the basis of these equations. Presents features of the proposed reactor, comparisons of circulating types, investigations of bubble-rise velocities, effects of transient conditions of vapor mass in steam chest, and bubble time delay functions yield favorable results. [From Abstract]

Technical report investigating the corrosion resistance of thorium and thorium alloys containing from 2 to 6% chromium, columbinium (niobium), titanium, zirconium and titanium-zirconium in distilled water at 95ºC. The true effects of the various alloy additions could not be determined because of the more marked effect of cold working. [From Abstract]

From abstract: "The rate of hydrolysis of TBP and the effect of the hydrolysis products in the Purex Process have been studied. Hydrolytic conditions may be encountered in the process which would lead to formation of dibutyl phosphoric acid, causing significant losses of tetravalent plutonium in stripping. This situation may be easily alleviated by reducing and stripping the plutonium in the trivalent state."

From abstract: "Neutron-irradiated uranium was electromagnetically separated to provide enrichment of the isotope of mass 236. The final isotopic abundance of U 236 was determined to be 95% in 1800 milligrams of uranium. Useful by-products of the program were 22 grams of 25% U 236 and 1100 grams of 99.7% U 235. These enriched materials have been made available for use on Atomic Energy Commission projects. Possible application of this separation process to recovery of the fuel from the MTR reactor is described."

From abstract: "Neutron-irradiated uranium was electromagnetically separated to provide enrichment of the isotope of mass 236. The final isotopic abundance of U 236 was determined to be 95% in 1800 milligrams of uranium. Useful by-products of the program were 22 grams of 25% U 236 and 1100 grams of 99.7% U 235. These enriched materials have been made available for use on Atomic Energy Commission projects. Possible application of this separation process to recovery of the fuel from the MTR reactor is described."

As originally installed, the primary process pump turbines in 190-B were arranged to accelerate considerably upon loss of BPA electric power supply to the Process Pump House. However, the acceleration comes too late to be of value in maintaining top of riser pressure within the first second or two, and the acceleration results only in maintaining final process water pressure and flow at values higher than needed. It is desired to limit the acceleration of the turbines to a relatively small amount in order to decrease the emergency steam demands and keep the combined steam demands of 100-B and 100-C Areas within the capacity of 184-B Boiler House, as outlined in Document HDC-2106, revised June 4, 1951. This report recommends that the desired results be obtained by simply reducing the speed setting of the turbine speed governors. No new equipment is needed. The setting of the emergency over speed trips would be left unchanged.

Operation, rehabilitation, and expansion of Hanford Works was undertaken by GE from Sept. 1946 to the end of 1950. As a result of engineering progress, graphite reactors continue to be the country`s primary source of plutonium in production quantities; at the end of 1950, the plutonium production rate from the Hanford reactors was 299% of the 1946 rate with a 67% increase in reactor facilities. Improvements to existing plant facilities and processes resulted in savings of $53.3 M; in addition, it would have been necessary, in order to produce the amount of Pu delivered through 1950, to have constructed facilities costing $225.4 M if the following improvements had not been made: an irradiation-stable uranium slug; annealing of graphite; increased operating power level of the reactors; and improved separation methods. Tritium production, health/safety, and community management are mentioned.

Summary: A study has been made of possible processes for the production of hafnium-free zirconium of a grade suitable to meet AEC specifications.

This is a progress report of the production reactors on the Hanford Reservation for the month of November 1951. This report takes each division (e.g., manufacturing, medical, accounting, occupational safety, security, reactor operations, etc.) of the site and summarizes its accomplishments and employee relations for that month.

Abstract: The Treasure Hill area consists of eight mining-lode claims in secs. 10 and 15, T. 9 N., R. 70 W., Larimer County, Colo. All of the workings were examined and samples were taken from most of them. The results of the examination indicate that there is little or no detectable radioactivity in the schist and granite of the area.

None

The fused fluoride-Inconel reactor system was studied under irradiation with nominal 19 Mev deuterons as supplied by the Berkeley 60-inch cyclotron. Chemical, metallographic, magnetic susceptibility, electron diffraction and X-ray diffraction studies were made on the as-received materials, one control run and two irradiated runs. No changes in the fused fluoride fuel were noted. Accelerated intergranular corrosion and increased grain size were observed in the irradiated Inconel specimens. This report is based upon studies conducted for the Atomic Energy Commission under Contract AT-40-1-GEN-1064.

Introduction: The general project of correlating soil properties with geologic information and with simple soil index characteristics, one phase of which is described in this report, consists in comparing soil properties with soil types and with their geologic history and environment in order to determine what correlations are possible.

A simple mass spectrometer using 60 degree focusing was set up to study the (illegible) of the ions produced by various types of sources. A schematic diagram of the apparatus is shown in Fig. 1, which is to a large extent self-explanatory. The isolation transformer was simply a piece of RG (illegible) cable about three feet long and was used in order to operate the source at high accelerating voltage allowing the collector to be at essentially ground potential. The collimating slits were 0.05 (illegible) wide and were space 4 (illegible-cm?) apart. The coarse slit immediately preceding the collector cup was 0.3 (illegible) wide. The electrometer was the integrating type which indicated the potential due to the charge collected on known capacitance. The vacuum tube voltmeter indicated the potential of the 0.5 (illegible) capacitor due to the total charge reaching the slit system. It thus served as a monitor of the source output for each firing. The neon lamp was a protection for the condenser against breakdown discharges of the tube.