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

Report discussing a study regarding rolling as a technique for making uranium fuel elements that are flat-plate and aluminum-clad.

The following report presents a discussion of the method for hydrodynamic problems, together with some new considerations that have arisen concerning the method.

From abstract: In 1953 the U. S. Geological Survey started the present program of uranium investigations on behalf of the U. S. Atomic Energy Commission in the San Rafael Swell, Emery County, Utah. Two areas within the Swell were selected and studied; one in the vicinity of Temple Mountain and the other at Green Vein Mesa.

In studies of the fabrication of fuel subassemblies for the supercritical-water reactor, the limited ductility of stainless steel-UO₂ fuel sheet made the fabrication of corrugated-flat-plate-type subassemblies impractical. A fabricable MTR-type assembly, 5/8 in. square and 30 in. long, was developed. Methods for edge cladding fuel sheet were developed and a brazing alloy, GE-75, was found to be corrosion resistant in supercritical water.

The objective of this test is to establish that scavenging of first-cycle wastes in the Bismuth Phosphate Plant will give a supernatant liquor, after the precipitate settles, that may be routinely cribbed. This test will also perform the functions: establish an effective scavenging procedure, shakedown the pH monitor, and train operational personnel. This document discusses test procedures and results.

This report describes the direct essential material requirements for processing a standard run through the precipitation separations process in effect on August 1, 1954. Flow sheet conditions are based on a starting maximum batch size of 300 grams of product at a uranium irradiation level of 215 MWD/ton. The essential material requirements are those used to process with 2.5 grams of Bismuth per liter in Extraction, First Decontamination Cycle volumes at 56% of the September 1, 1946 standard, and Second Decontamination Cycle through the Lanthanum Fluoride Product Precipitation volumes at 49% of this standard.

Abstract: "The cross section for the reaction Al²⁷(p,3pn)Na²⁴ has been measured for proton energies between 30 and 350 Mev relative to the cross section for the reaction C12(p,3pn)C11, and the absolute magnitude determined by matching with data measured with a Faraday cup at 350 Mev and at 31.5 Mev."

Report discussing a test for lethals resulting from the recombination of X-chromosomes in ten different stocks wild-type Drosophila melanogaster.

Studies in the 321 Building dissolver during December 1953 and January 1954, were successful in developing a laboratory-proved mercury-catalyzed dissolving flowsheet into a suitable plant procedure. However, this flowsheet was not adapted for Redox plant operation because of uncertainty about the possible presence of hydrogen above the lower explosive limit in the off-gases. Subsequent laboratory work has resulted in a better understanding of the hydrogen evolution, and has resulted in developing low hydrogen evolution flowsheets. When one of these flowsheets is selected for further work, it will be tested in the 321 Building dissolver with non-irradiated slugs to provide information for scaling-up the single-slug laboratory data to a plant-scale operation. It is the purpose of this memorandum to outline the factors considered to be pertinent to the 321 Building investigation, to be used as a guide in making preparations for the runs to be performed.

Tube 1794-C was removed from the pile as a leaker on July 15, 1954. The tube had been in-pile since startup and had contained a charge of 32 ``C`` metal slugs just prior to discharge. The tube was slit and examined at the 105-DR underwater viewing facility by Pile Coolant Studies tube examination personnel. A report is made of the examination of tube 1794-C which revealed areas of severe pitting damage. This damage was apparently caused by cocked slugs abrading the tube. The attack was great enough to cause perforation of the tube at about 27 feet from the rear Van Stone flange. Examination of the slugs showed that a considerable number had been cocked. Evidence of severe tube scarring and rib grooves was found on the slugs. Strikingly similar examples of pitting and grooving were observed on flow laboratory minitubes and slugs exposed in high velocity water. It is concluded that the damage observed both in- and ex- pile was caused by the chattering of misaligned low density slugs in a high velocity stream. If the number of in-pile occurrences of this attack becomes excessive it is recommended that the water flow rate in tubes containing ``C`` metal slugs …

Recent successes with the use of metal ferrocynanides, particularly nickel ferrocyanide, for the removal of cesium from Uranium Recovery Process wastes prompted an investigation into the use of this carrier for the removal of cesium from wastes produced in the coating-removal and first-decontamination-cycle steps of the Bismuth Phosphate Process. Both in-line treatment of the wastes currently produced and treatment of supernatant liquids from wastes already stored in underground tanks were considered.

This document defines the basic criteria to be used in the preparation of detailed design for Project CG-558, Reactor Plant Modification for Increased Production and for Project CG-600, 100-C Area Alterations. It has been determined that the most economical method of increasing plutonium production within the next five years is by the modernization and improvement of the 100-B, 100-C, 100-D, 100-DR, 100-F, and 100-H reactor plants. These reactors are currently incapable of operating at their maximum potential power levels because of a limited availability of process cooling water. As a result of this programs, it is estimated that 1650-2350 megawatts of total additional production will be achieved. The purpose of this document is to set forth the design for certain modifications and additions to Hanford reactors and their supporting facilities as required to obtain higher power levels and improve the safety of reactor operation.

This document presents a summary of work and progress at the Hanford Engineer Works for July 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 reports 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.

The purpose of this document is to provide a means for estimating the age of ruthenium ground contamination when the ration of Ru 103 activity to Ru 106 activity in the contamination is known.

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Abstract: From December 1953 to May 1954 an extensive airborne reconnaissance program was conducted in northwestern Arizona (Arizona Strip) and southwestern Utah. Five surface anomalies were detected, one of which has possible commercial value. All anomalies are within the boundaries of National Park Service jurisdiction, consequently, this report is not for public distribution until clearance is obtained from the National Park Service. A preliminary airborne reconnaissance program was also conducted in the Richfield area. No anomalies were discovered.

Introduction: Three matters discussed in the main report on the investigation of the suitability of Prepakt concrete for mass and reinforced concrete structures, issued in October 1951, required further study. These matters are (a) the properties of Alfesil, (b) the permeability of Prepakt concrete, and (c) the resistance of Prepakt concrete to natural weathering.

Portions of the Hanford Reservation in 1954 had significant particulate contamination from the Redox process. This paper is about the methods used to decontaminate the Reservation. The two methods are decontamination and access control. A general description of the ideas and benefits of each method is given. (MB)

Abstract: Approximately 10 square miles of mainly igneous rocks of the western Mojave Desert were covered by this airborne radiometric survey in 173 hours of flying time.

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Herman Lurie's weekly report for the sugar market. Details include prices, distribution, refiners, and quotas.

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

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