Report issued by the Bureau of Mines over investigations of coking-coal reserves of Mercer County, West Virginia. Methods used, and measurements of coal reserves are listed. This report includes tables, and maps.

From abstract: Uranium on the Hooper Tunnel level of the Crescent mine, Shoshone county, Idaho, occurs in two red, iron oxide-stained radioactive zones in and along the hanging wall of Alhambra fault.

Management of first-cycle wastes from the Bismuth Phosphate Plant using Nickel Ferrocyanide scavenging is described.

Report that summarizes unreported neutron-yield data for the MnSO₄ tank method. Other yield measurements had been reported in other quarterly reports prior to the completion of this one.

Abstract: "From neutron-yield measurements made with a MnSO4 detecting solution, the average number of neutrons produced per inelastic event is determined for a series of elements from lithium to uranium for 340-Mev protons, 190-and 315-Mev deuterons, 490-Mev He3 ions, and 90- and 160-Mev neutrons. The results are analyzed in an attempt to understand the total yield measurements for thick targets and to explain the variation of yield with the atomic number of the target."

Abstract: "The problem of maintaining livable oxygen and carbon dioxide pressures in a closed space in which men must live leads to consideration of the possible use of the photosynthesis of green algae. A calculation based on the known respiratory rate of man and the photosynthetic rates of Chlorella indicates that it would be feasible to use algae for this purpose."

From abstract: "Within the framework of age theory an expression is developed which represents the probability of a neutron being reflected with an energy loss corresponding to age, v, as a function of reflector thickness."

The purpose of this document is to present a capacity study of the existing UO{sub 3} Plant Nitric Oxide Absorption System.

Abstract: Numerical information necessary to an experimental study of the polarization of bremsstrahlung is presented. One may conclude that it is possible to produce significantly polarized γ-ray beams with existing electron accelerators. These beams will provide a new tool for the study of photonuclear reactions over a wide range of energy.

None

From April, 1951 to Aug, 1954, New York Shipbuilding Corp. carried out a subcontract with E.I. du Pont de Nemours & Company that was without parallel in the shipyard`s history. The work, designated the NYX Project for reasons of security, was vital to the operations of the Savannah River Plant, Aiken, S.C., which was then being designed and constructed by du Pont for the Atomic Energy Commission. It consisted of three broad parts: developmental and experimental work; fabrication and testing of a prototype unit; fabrication of production units. Five production units were ultimately built, one of them converted from the prototype. All were fabricated from stainless steel, and involved welding techniques, control of thermal distortion and tolerances never previously attempted on assemblies of comparable size. Du Pont`s technical experience and the background of New York Ship in heavy construction, particularly in the fabrication of naval gun turrets, were combined from the outset to resolve the difficult fabrication problems that occurred almost daily. Representatives of both companies worked together as a team in the shops and at supervisory levels to an unprecedented extent. The report is intended primarily to summarize New York Ship`s part in the project, but also includes some …

This document presents a summary of work and progress at the Hanford Engineer Works for August 1954. The report is divided into sections by department. A plant wide general summary is included at the beginning of the report, after which the departmental summaries begin. The Manufacturing Department report plant statistics, and summaries for the Metal Preparation, Reactor and Separation sections. The Engineering Department`s section summarizes work for the Technical, Design, and Project Sections. Costs for the various departments are presented in the Financial Department`s summary. The Medical, Radiological Sciences, Utilities, and General Services, Employee and Public Relations, and Community Real Estate and Services departments have sections presenting their monthly statistics, work, progress, and summaries.

At HAPO the protection of employees from nuclear radiations has paralleled or preceded the emphasis on atomic products production. The production of atomic products on the scale for which HAPO was designed presented voluminous problems in employee education, radiation detection, shielding, and indeed, fundamental research to determine working limits for the various types of radiation exposure which would necessarily be encountered, and to determine working limits for the deposition of radioactive isotopes and mixtures of isotopes in the human body. Since the time radioactive materials first arrived at HAPO and the start-up of the first HAPO reactor on February 23, 1944, there has been a fundamental philosophy that all employee exposure to nuclear radiations should be maintained at a minimum, as opposed to just some level of exposure below the accepted permissible limit. It was with this philosophy in mind that the many achievements and advances in the science of radiation protection at HAPO have been forthcoming. These advances in radiation protection ar discussed in this report.

On July 27, 1954, 965 grams of plutonium alloy contained in three standard quart size ice cream cartons were being removed from the process line by two process operators using the plastic bag technique. Shortly after the plastic bag scaler had been energized a brown spot appeared on the plastic bag. The glowing turnings burned through the containers and plastic bag and continued to burn until completely oxidized. Personnel contamination was minor and readily removed. The contamination was confined to the room of the incident and was deposited in gross amounts in the area surrounding Task IV and V. This report includes a description of the incident and subsequent decontamination activities and a summary of plutonium recovery. Facts unknown about the incident and the reasons for these facts not being known are discussed. Plans for the future for reducing the possibility of recurrence of a similar incident are formulated.

A new slug for U-233 production consisting of a solid thorium core externally jacketed by a thin Oralloy foil is described. Advantages of this system are pointed out. The bulk of this report concerns itself with the long-term changes of reactor parameters as the foil slug is irradiated at constant specific power (kilowatts per foot). Isotope yield curves are also presented.

The examinations of seven process tubes are covered in this report. Tubas reported on are 3362-B and 0561-C. these were removed under PT-105-522-P. ``Routine Examination of Process Tubes``. Tubes 2572-C and2679-C were operating under PT-105-519-E. ``Raising Permissible Outlet Water Temperatures of Certain Tubes at C Pile``. In tube 2679-Z a rupture occurred during its operating period. These tubes (2572-C and 2679-C) were smaller diameter process tubes such as used in B, D, F, DR, and H Piles. Tube 2772-C was removed because of a suspected rupture. Tubes 3571-D and 2170-D were removed under PT-105-525-E. ``Effects of Water Quality on Pile Operation``. Visual inspection was made of the inside and outside surfaces before and after removal of the film. This work was performed in the 105-DR storage basin. Samples varying from one to four inches in length were taken from each section and transferred to the 108-B metallurgical laboratory for closer examination as regards to depth of pitting, 72-S cladding thickness, and wall thickness. The results shown in this report such as pit depth, 72-S cladding thickness and 2-S aluminum thickness are taken at specific points in each section, on what appeared to be the severest attack.

Abstract: A study, consisting of field and laboratory work, was undertaken in an endeavor to establish possible structural mineralization controls associated with the copper-uranium occurrences in the Willaha area, Coconino County, Arizona. Uranium mineralization, apparent at present, is localized along small fissures and vugs and in certain beds and lenses of the middle member of the Kaibab formation(Permian). It is associated with copper and iron oxide staining. Though no definite ore controls were disclosed by this study, at least a limited program of shallow drilling is warranted on the property. This sub-surface exploration should determine possible extensions of known mineralized areas, explore surface radiometric anomalies, and provide data for the determination of possible guides to ore. Deeper exploration may encounter mineralization in other horizons of the Kaibab limestone.

"A design study is presented for a sodium cooked, graphite moderated power reactor utilizing low enrichment uranium fuel. The design is characterized by dependence on existing technology and the use of standard, or nearly standard, components. The reactor has a nominal rating of 167 thermal megawatts, and a plant comprising three such reactors for a total output of 500 thermal megawatts is described. Sodium in a secondary, non-radioactive, circulation system carries the heat to a steam generator at 910 degrees F and is returned at 420 degrees F. Steam conditions at the turbine throttle are 600 psig and 825 degrees F. Cost of the complete reactor power plant, consisting of the three reactors, and on 150-megawatt turbogenerator, is estimated to be approximately $43,165,000."

"The Atomic energy Commission has undertaken a development program to provide the technology needed for the evaluation and economic design of nuclear power plants. This program is to be carried out during the next five years at several national laboratories and industrial organizations. The Sodium Graphite Reactor (the SGR) is one of those to be investigated and experimentally tested as part of this 5-year effort. The program on the SGR is intended to expand our area of information covering sodium-graphite technology, experimentally demonstrate the feasibility of this reactor complex and extend its performance limits, and apply in information developed to designs suitable for the full-scale nuclear power plant. As a principal part of this program, a Sodium Reactor Experiment (the SRE) is to be constructed and operated; it will be the major experimental facility in which the performance of this reactor will be studied and new technological advances tested. This report continues an earlier series 2-7 in which previous work on the SGR and the SRE has been described. In this report, the progress on the program is described in two main sections. Section A is devoted to work relating to the general technology of Sodium Graphite Reactors, and to …

Herman Lurie's weekly report for the sugar market. Details include tons of sugar, prices, distribution, and sellers.

Herman Lurie's weekly report for the sugar market. Details include prices, distribution, sellers, sales, and tons of sugar.

Herman Lurie's weekly report for the sugar market. Details include prices, tons of sugar, distribution, and sellers.

Daily cash report for Imperial Sugar Company including a list of large withdrawls for the months surrounding the date showing the daily expenses and estimated balance for each entry. It also lists scheduled payments for bank loans.

None