Report issued by the U.S. Bureau of Mines on the study of oil recovery through gas-injection techniques. The report discusses these secondary oil recovery methods in Cabin Creek field in West Virginia. This report contains maps and tables.

From introduction: Silicon carbide is being considered as a basis material for nonmetallic fuel elements because of its high thermal conductivity, low nuclear cross section, high resistance to thermal rupture, and high degree of stability at high temperature in air. A requirement of the fuel elements is that they be thin and have as low porosity as possible. One shape of element under consideration is 0.050 to 0.070 inch thick by a few inches in width and breadth.

Abstract: "The amount of hydrogen normally present in zirconium and zirconium alloys suffices to reduce their ductility greatly in an impact test at room temperature, after slow cooling from 600 F. Quenching from 600 F or above gives high impact strength, as does removal of hydrogen by high-temperature vacuum annealing. This report discusses the evidence on hydrogen embrittlement, the diffusion, solid solubility, and equilibrium pressure of hydrogen of hydrogen in zirconium, the microstructure, and the effects of hydrogen and heat treatment on the mechanical properties of zirconium."

This is a photogeologic map scale 1:24,000 of Elk Ridge-8 Quadrangle, San Juan County, Utah.

This is a photogeologic map scale 1:24,000 of Verdure-5 Quadrangle, San Juan County, Utah.

This is a photogeologic map scale 1:24,000 Elk Ridge-1 Quadrangle, San Juan County, Utah.

This is a photo-geological map of the Clay Hills-15 quadrangle of the Navajo Indian Reservation in San Juan County, Utah.

This is a photogeologic map scale 1:24,000 Setsiltso Springs-4 Quadrangle, Navajo Indian Reservation, Apache County, Arizona.

This is a photogeologic map scale 1:24,000 of Agathla Peak-4 Quadrangle, Navajo Indian Reservation, Navajo County, Arizona.

This quarterly progress report details ongoing work at the Oak Ridge National Laboratory as part of the Aircraft Nuclear Propulsion Project. Topics of discussion include reactor theory and design, shielding research, materials research, appendixes with information on ongoing analytical chemical studies.

From summary: "The hazards due to possible chemical explosion and detonation of the dissociation gases in homogeneous-reactor systems have been considered."

"This symposium is concerned with the basic aspects of radiation effects. When we turn to the genetic effects of radiation in mammals, there are so few aspects on which there is any information that the problem of sorting out the fundamental findings has hardly arisen. In this paper it will, therefore, be possible to survey most of what is known and pass on to a consideration of what is needed next. Since one of the purposes of this symposium is an interchange of views between investigators in different fields, an attempt will be made to avoid technical details. Among the practical needs in mammalian radiation genetics is a pressing one for more data on which to base estimates of the genetic hazards of radiation in man. The present paper will be concerned largely with this problem. Our own work is directed primarily in this direction, our objective being to uncover some of the basic facts in at least one mammal-the mouse. Before discussing the experimental work, however, it seems desirable to consider some of the general features of the genetic hazard of radiation."

From summary: "The influence of the structure of phosphate esters on the distribution coefficient of uranium between solutions of these esters in carbon tetrachloride and aqueous nitrate solutions has been studied. Esters of secondary alcohols showed higher distribution coefficients than primary alcohols. Phenyl esters extracted less uranium than alkyl esters, and the presence of other negative groups also resulted in less extraction. Compounds containing carbon to phosphorus bonds gave higher distribution coefficients than the corresponding esters, and the distribution coefficients increased with the number of such carbon to phosphorus bonds. Tributyl phosphine oxide (with three carbon to phosphorus bonds) showed high distribution coefficients with many salts, including uranyl nitrate, uranyl sulfate, uranyl chloride, thorium nitrate, plutonium (IV) nitrate and some of the fission products in nitrate solution. It is planned to study these and similar compounds further."

This quarterly progress details the ongoing work of the Protective Equipment Evaluation Program at the Oak Ridge National Laboratory. Topics discussed include aerosol generation, penetration studies, particle size measurement, and an appendix with analytical methods.

From introduction: "The tube arrangement covered in this report was proposed in June, 1950, as a means of halving the weight and volume required for the heat exchanger. Ideally, the pressure drop across this arrangement should be little more than that required to overcome the skin friction on the tube surfaces. If the pressure drop across the tube spacers and in the cross-flow regions can be kept low, this ideal can be approached. much of the test work covered in this report was devoted to this phase of the problem."

From abstract: "This report presents the laboratory development of the MTR-RaLa Process for the production of barium140 from Materials Testing Reactor assemblies." The laboratory studied four possible chemical schemes with the final process being chosen "on the basis of chemical yield and purity of product, ease of recovery of uranium235, simplicty of equipment, and overall time required for processing" (from introduction).

A leaflet describing the Farm-Storage Facility Loan Program of the U.S. Department of Agriculture's Commodity Credit Corporation (CCC).

An examination of the process scheme for handling present and future 231 Building supernatant solutions is necessary to forecast the effects of placing one of the processing facilities (224B) in a standby status and to ascertain if rescheduling of any of the supernatant solutions to 202S will be necessary. The examination indicates the 231 Building process supernates and cell cleanouts together with the 221, 224T Buildings acid washes and the 234-5 Building returns can be processed through the 224 T Building as additions to regular runs or master recycle runs when T Plant is processing as much as 41.6 tons/month of 600 MWD/T material and S Plant is processing 120 tons/month of similar material. The processing rate through, 224 T Building to satisfy these conditions is seventy-six runs per month. This total is divided into 63 regular runs plus 13 meter master recycle runs. The number of master recycle runs are primarily dependent upon the T Plant rate in as much as only one master recycle is directly required for each 35 tons processed through S Plant.

The following report describes the process to determine the method for determination of americium in the presence of plutonium and uranium.

Report containing results of a study regarding concentration of radioiodine in edible plants fed to animals.

The following report investigates tests on diffusion length and contamination performed on graphite laid up in 105-DR and 105-H piles.

Report describing the effects of pile irradiation on fuel materials and coil springs for the Submarine Intermediate Reactor. The investigation was called for by Hanford Irradiation Request No. 79. Results of investigation are detailed in the report.

The following report provides complete data and test procedure from hot water corrosion tests of type 502 stainless steel.

This report presents data recorded during a program made to improve uranium slug quality in January, 1952, to determine what improvements could be made in the welding process.