This report provides an overview of a gridded ionization chamber, instructions on how to operate the instrument, and then discusses the performance of the instrument so far.

The purpose of this report is to provide calculated liquid flow pressure drop data for the 1706-KER recirculation loops.

Monthly newsletter of the High Plains Underground Water Conservation District No. 1, discussing the field of underground water. Topics include profiles of water conservation research, annual pre-plant soil moisture survey data, annual Winter Water Level measurement data, and information about the latest water conservation tips.

Report discussing a reconnaissance study performed in September and October 1954 of the Bisbee district in Cochise County, Arizona. The purpose of the study was to determine the area's suitability for a detailed study of the relation between uranium and hypogene mineral zoning.

A report regarding a drilling project at Tenderfoot Mesa, Mesa County, Colorado.

A general method is developed to allow calculation of the critical buckling of an assemblage of fissile regions coupled by neutron leakage. Consideration is given both to regions embedded in vacuum and in material media. Several cases of simple geometry are further developed to illustrate the theory.

The enthalpies and heat capacities of seventeen fluoride mixtures in the liquid state have been determined using Bunsen Ice Calorimeters and copper block calorimeters. The fluoride mixtures were composed of the fluorides of two or more of the following metals: lithium, sodium, potassium, beryllium, zirconium, and uranium. The enthalpies and heat capacities of most of these mixtures were studied in the solid state also. Estimates of the heat of fusion have been made. General empirical equations have been developed which represent the enthalpies and heat capacities of the fluoride mixtures in the liquid and in the solid state.

This paper presents the results of a series of buckling measurements involving the use of enriched uranium rods (1.007% by weight U²³⁵) in light water. The effect of replacing a water reflector with one of uranyl nitrate solution of two different concentrations, 536 and 188 grams of U per liter of solution was investigated for the 0.925" rods with the 1.74 H₂O/U-volume ratio in the core. Some information was also obtained on the extrapolation length to be used in unreflected cases. The application of theory to these lattices, and others, is given in an appendix under separate title, "Buckling Calculations for One Per Cent Enriched Uranium-Water Rod Lattices."

Among the safety considerations for the Purex plant is the question of flammability limits for the diluent-air system. The present note attempts to delineate the temperature regions of concern by utilizing hydrocarbon flammability data available together with information on the vapor pressures of the systems.

A report, with accompanying maps, showing distinguishable lithologic units and occurrences of uranium in outcrops in the Pumpkin Buttes area of the Powder River Basin

Cadastral map of Bailey County showing plats and and county boundaries. There are illustrated ducks decorating the title and smaller birds around the lakes near the center of the map. Scale ca. 1:66,666.

Abstract: To date uranium deposits have been confined to a thin sandstone in a zone near the contact of the Middle and Lower Members of the Toreva Formation and as a leach in the Lower Sandstone Member. On a large scale the deposits are apparently restricted to zones of tectonic deformation. Locally mineralization is primarily controlled by small intraformational channels and cross bedding, and is usually associated with carbonaceous material and quartzose sand lenses.

The methods of analysis given in this report are those which were used in the Analytical Chemistry Division of the Oak Ridge National Laboratory for analyzing samples which were derived from the experimental work on the separation of the isotopes of boron by chemical exchange. The samples consisted principally of boron trifluoride solutions in anisole (methyl phenyl ether, CH30C6H5). The boron concentration ranged from a few parts per million to 5 or 6 per cent. Boron was determined on all samples. During the early stages of the project, iron and copper were occasionally determined, while a limited number of aqueous solutions and water extracts of anisole solutions of BF3 were analyzed for fluoboric and hydroxyfluoboric acids, boric acid, total boron, and total fluoride. Boron was determined by the use of either a spectrophotometric or volumetric method, depending on the amount available. Initially, if the amount of sample and boron concentration were such as to provide a total of at least 2 to 4 mg of boron, the volumetric method was utilized and found to be satisfactory. For smaller amount, the spectrophotometric method was used. Later, because of its greater speed and simplicity, the spectrophotometric method was used for samples in …

This report discusses a nuclear spectroscopic study of the radiations resulting from the electron capture decay of Ta-176, Ta-177, and Ta-178, analyzing data of nuclear decay schemes.

Report discussing the location, occurrence and chemical character of ground water in the Morrison formation near uranium-vanadium ore mineral deposits. Conclusions are included.

Report discussing a study on the Central City district and adjoining mining areas to determine the geology and economic importance of the uranium occurrences in the region.

A preliminary report discussing a diamond-drill exploration in the southern part of the Uravan District.

Report discussing a preliminary study of limonite sourced from nine localities of different types through Colorado, Utah and Wyoming, in the spring and fall of 1953. This study aimed to establish criteria for differentiating uranium- and thorium-related limonite and limonite not related to uranium or thorium. The report is divided by descriptions of each locality.

A report regarding a preliminary study of radioactive limonite localities in Colorado, Utah, and Wyoming. Concerns work done on behalf of the Division of Raw Materials of the U.S. Atomic energy Commission.

Reflected cylindrical exponential columns of bare and natural uranium were constructed of stacked plates of oralloy (93.4%) and tuballoy. Average concentrations of U235 ranging from 0,72% to 9.18% were investigated. Flux distributions, buckling values, and spectral indices were obtained. The indicated U235 concentration for infinite critical mass is about 5.5%.

A report about the properties of dilute uranium alloys. The mechanical properties of cold worked sirconium and zircaloy 2 at temperatures up to 500 C ore being determined.

The work of the BNL Waste Processing Development Project has been concerned with developing means to accomplish three main objectives in handling radiochemical wastes. One is to reduce the corrosiveness of the waste. At present some wastes must be stored in SS vessels at high cost, since other tankage would not resist corrosion for any length of time. Hanford has solved a part of this problem by storing a neutralized or alkaline waste which can be contained more cheaply in 1020 steel vessels, although neutralization increases its total volume 50 percent over the original acid solution volume. Another aim in waste disposal is to reduce the mobility of the water. Although equipment is checked and double checked, and corrosion resistance is assured by extra thick-walled vessels, the possibility exists that a leak in such storage tanks may develop. At such times the solution may be carried by ground water into populated areas, whereas a relatively immobile waste would remain a local problem. A third and very important consideration is a desirable reduction in total waste volume. Since costs of waste storage are propositional to the volume stored, any reduction in total volume will reduce the total cost.

The purpose of this document is to review the stud situation at Purex and make such recommendations as possible for use in any future canyon installations.

This report describes a production scale procedure for purifying and concentrating the plutonium contained in the stripping solution from a tributyl phosphate extraction process. Conclusions from exploratory laboratory tests on the variables effecting the efficiency are included.