Report discussing the possible existence of pegmatites containing beryllium deposits in the granite stock in the vicinity of Mount Antero and White Mountain, Chaffee County, Colorado.

The following handbook was made for the purpose of: (1) to give a semidetailed description of the testing reactor, and (2) to explain, in so far as possible, the reasons for the design.

A report of quarterly results of research and development directed towards establishing new techniques and instruments towards improving present methods for determining levels of radioactivity accurately and safely.

This report provides a table that summarizes the data taken from investigations of gamma radiation of the Bulk Shielding Reactor in an iron-water mixture. The results are plotted on a graph also provided in this document.

The following report analyzes the characteristics of eight chelated uranium complexes and seven uranium ammines, prepared from the reaction of organic solutions of uranium salts with complexing agents and organic bases.

A preliminary reserve statement, regarding Reserve Blocks B and C, located in the Legin group Area, in San Miguel County, Colorado.

A preliminary reserve statement regarding Reserve Block D, of the Legin Group Area, located in San Miguel County, Colorado.

From introduction: The present report summarizes the indicated and inferred reserves which have been found to date by the drilling in Club Mesa, Montrose County of New Mexico, and includes an estimate of the potential reserves predicted for the area. It also includes a statement of plans for additional drilling. A final report will be prepared on the completion of the drilling planned for 1951.

From abstract: This report comprises data derived from 53 prospect drill holes drilled by the Davison Chemical Corp. in the eastern part of the Bonny Lake mine, Polk County, Fla.

Report issued by the U.S. Bureau of Mines to evaluate the known reserves of coking coal in Pike County, Kentucky. The properties of coal and coal blends from the area are presented. This report includes tables and maps.

From introduction: In an effort to stimulate the search for uranium deposits among professional geologists and mining engineers, the following pages present a brief summary of some of the pertinent facts and ideas concerning the geology of uranium deposits evolved by many individuals who have been actively engaged in uranium exploration. This work has been done by members of the U. S. Geological Survey, the U. S. Atomic Energy Commission, geological surveys of several other countries, mining companies, and several educational and research institutions.

Report documenting the suitability of Arkansas for plant locations to produce synthetic liquid fuels, based on raw materials such as coal, natural gas, oil shale, and oil-impregnated strippable deposits.

Report documenting the suitability of Illinois for plant locations to produce synthetic liquid fuels, based on raw materials such as coal, natural gas, and oil shales.

The second volume of a report documenting the suitability of Illinois for plant locations to produce synthetic liquid fuels, based on raw materials.

Report documenting the suitability of Kansas for plant locations to produce synthetic liquid fuels, based on raw materials, water sources, and local interest.

Report documenting the suitability of Maryland for plant locations to produce synthetic liquid fuels, based on raw materials, water sources, and local interest.

Report documenting the suitability of Oregon for plant locations to produce synthetic liquid fuels, based on raw materials, water sources, and local interest.

Monthly report of the U.S. Geological Survey's trace element investigations including an outline of field work, laboratory work, and staff activities that have been completed or are in process.

Abstract: "Steady states decomposition product partial pressures of water exposed to an epithermal neutron flux of about 2 x 10-11, at 235F, were 0.4 to 0.65 psi. Recombination studies were made by adding hydrogen and oxygen gases to water under irradiation at different temperature and flux levels. The data show a significant effect of temperature on the rate of pressure drop of the added hydrogen and oxygen. In operating at two flux levels, 1.2 x 10-11 and 2.0 x 10-11, no difference in the rate of pressure drop with flux could be detected with the instrumentation on the test apparatus."

Abstract: "Decontamination factors of the order of 10-4 were obtained for Beta and Gamma emitters present as fission products when uranium was precipitated from 50 mC activity level solutions as uranyl oxalate under normal uranium yield conditions for three cycles (~60%). Factors of the order of 10-3 were obtained by the use of this reaction with similar solutions under relatively high uranium yield conditions for three cycles (~90%). The uranium peroxide precipitation reaction proved to be of no value on such solutions, yielding decontamination factors of only 17.1 Beta emitters and 1.2 for Gamma emitters for three cycles."

It has been found relatively easy to form uranium in the gamma phase temperature range by hot pressing, forging, or extrusion. The metal is quite plastic and flows readily to form a shape. Several temperatures from 800 degree C to 1000 degree C were investigated. No forming difficulties were experienced with the metal at the several temperatures concerned. The major difficulty in gamma phase hot pressing or extruding was associated with the tools. Metals or ceramics were not successful as tools for one or more reasons concerned with: lack of hot strength, reactions with the uranium, failure in thermal shock, and tendency to spall. Graphite was found to be the best material available, but it is not entirely satisfactory because of low strength. Uranium formed in the gamma phase possesses some refinement of grain structure as compared with as-cast metal; however, the grain size is quite large. No physical properties of the gamma phase formed metal were determined.

The following report discusses neutron sources in reactors, discussing general conditions of the study using a flux reactor.

This report helps determine tritium in the range of 0.1 to 100% in other gases using an ion chamber that is analyzed within this report.

The following report provides data describing the total electron beam current as a function of A-12 beam radius. The beam is investigated using the provided equations.