"The following report is meant to serve a two fold purpose. First, it is the quarterly report of the homogeneous reactor project for the Technical Division of Oak Ridge National Laboratory. Secondly, it is a description and general feasibility discussion of a 200-1000 K.W. pilot model, homogeneous reactor."

The following report provides the analysis of a large number of unreported data--taken during a study described in report HW-15230--containing density values obtained for solutions of uranium and nitric acid in tributyl phosphate-carbon tetrachloride solutions.

The following report provides results taken from a sodium level indicator developed at Sacandaga using electrical resistance as the principle.

The following report discusses special shielded containers, called coffins, that are used for removing beam hole plugs from the reactor, transporting them to plug storage and inserting them therein. This report focuses on the handling of dummy and experimental beam hole plugs.

From introduction: This report represents an effort to assemble, relate, and evaluate available information about possible primary uranium mineralization in the state of Arizona. This is the initial step in preparation for a system ratio field study of the state.

"Changes, corrections and additions to the original report are included in this addendum. These are brought about by further development of the design by Blaw-Knox, AHL and ORNL. The changes in the original wiritings are listed below in accordance with the main headings, pages and paragraphs to which they apply. Following this is a list of the contemplated personnel in the MTR program. This listing sets out the number of offices and the office furniture requirements. Also numbers for lockers, showers, toilets and rest rooms are set forth. Although the listing includes all major buildings planned for the site, it is included here since the reactor building wing is more markedly influenced by office requirements."

"Changes, corrections and additions to the original report are included in this addendum. These are brought about by further development of the design by Blaw-Knox, ANL and ORNL. The changes are listed in accordance with the main headings, pages and paragraphs to which they apply."

Abstract: "A method for the potentiometric titration of uranium with ferric sulfate is described. This method provides a rapid and accurate way of determining the element in solutions free from interfering ions. Application of the method to analysis of pure uranium compounds and to uranium recovered from contaminated solutions by suitable procedures is briefly discussed."

Abstract: "A number of direct current conduction type electromagnetic pumps for liquid metals were constructed. Pumping capacities of over 400 gpm and efficiencies of over 50 percent were obtained. NaK alloy at temperatures up to 400 C was used in the test. The large currents required were obtained from rectifiers or from a homopolar generator constructed for the purpose."

The problem of the separation or enrichment of isotopes is as old as the knowledge of the existence of isotopes of stable elements. The article focuses on the mass-dependent property of atoms continuing to be investigated in laboratories to test its usefulness for new solutions to this problem.

The following report describes the design and construction of the reactor building wing, designed to attach to the reactor building for the Argonne National Laboratory.

The following report discusses the building design and development of the reactor building, Building 1105, for Argonne National Laboratory, that is meant to house the reactor.

This is a progress report on the carbonate process, compiled by the chemical development department of the Carbide and Carbon Chemicals Corporation's Y-12 plant, covering the month of September, 1949. In the previous month, the problem of immediate interest to the Monticello operation were listed. Projects that were left incomplete during that time were continued during this month, as well as a brief investigation of the process in which raw ore is leached with sodium carbonate, the sands and slime separated, the sands leached with acid, and the slimes roasted in a pellitized form.

Abstract: "Crystal system, crystal habit, and principal refractive indices, of uranyl hydrogen phosphate tetrahydrate, uranyl ammonium phosphate trihydrate, and uranyl phosphate tetrahydrate are reported. A procedure for differentation of these three compounds using this data was developed."

The following document analyzes studies to test the use of asphalt as a fast neutron moderating substance to be incorporated as a part of a pile shield.

The following report summarizes the data taken from a series of measurements on the combustion and ignition properties of hexone. The experiments were taken at the Bureau of Mines Central Experiment Station by their personnel, and the samples were given to them by KAPL and Hanford.

This is a progress report compiled by the chemical development department of the Carbide and Carbon Chemicals Corporation's Y-12 plant, discussing work on the carbonate (Monticello) process, as well as the recovery of uranium and vanadium from carbonate liquors.

From introduction: "The present report reviews the work conducted on the development of new cements other than magnesium oxychloride during the period from August, 1943, to October 1949. As in the previous reports, the total water contents reported represent the hydrogen combined as water and that which may be combined as a compound other than water."

The following document presents designs and blueprints to the bubble-cap column built to replace a nitric acid concentrator.

From introduction: "The present report covers the results of an extended investigation of magnesium oxychloride cements and concretes. In this study the effects of the composition of the cement or concrete on its physical and mechanical properties were determined. In addition, the stability of the mixes was observed."

The following report is a quarterly report by the Monsanto Chemical Company for liquid waste disposal research, covering the period between April 1 to June 30, 1949.

The following document describes the process of rare beryllium extrusion using graphite introductory cones with the purpose of finding a lubricant which would decrease excessive friction between the billet and prose parts.

The following report covers the results of a general program that was conducted at the Oak Ridge National Laboratory to investigate the effects on plastic materials of exposure to radiation in the pile. In the investigation, several plastics were irradiated, and on removal from the pile, their rates of decay were determined by measurement of gamma activity in an ionization chamber.

From introduction: "This is the first report on the study made of the possible power recovery without excessive cost, from the operation of the Brookhaven reactor."