Report discussing a method for the stepwise calculation of the number of transfer units utilized in a given solvent extraction operation. "Use of the method results in a very appreciable saving in time of calculation with an error of 1.5% for the runs tested. The error tends to become smaller with increasing total numbers of transfer units involved."

A report discussing an experiment conducted to determine the effect of radiation on the melting point of Tempilaq, a commercially available, temperature-indicating liquid.

Report discussing the results of research conducted by the Hanford Works Analytical Research Group during the period from March 1949 to April 1949.

Technical report including multiple lectures on nuclear science and engineering, planned to survey the theories, designs, operations, and experimental facilities of the Brookhaven Nuclear Reactor.

Technical report outlining the differences in conductivity of AGOT graphite and AGHT graphite.

This report discusses a series of investigations for biological and biochemical study of chronic exposures of animals to neutrons through an irradiation procedure.

Abstract: "The analysis of hafnium and zirconium by the copper spark technique is presented for solutions of HCl, HF, and HClO4 acids. The special techniques of electrode protection and vacuum drying of perchloric acid samples are outlined. Also given are the working curves and deviations of both elements."

From abstract: "The means of preparing uranium trifluoride are discussed. The most practical method is the reduction of uranium tetrafluoride with uranium although reduction with hydrogen or atomic hydrogen may also be feasible...A literature survey and discussion of other means of preparation are given."

Abstract: An electronic device has been developed for indication at a distance and simultaneous automatic correction of changes in density, temperature, and interface level of polyphase solutions.

Report describing the radioactive energy output of U slugs from the Clinton pile. Outputs were measured in a calorimeter. Results have been calculated to watts per gram and compared with previous reports.

Report discussing the research done on volatile "X" compounds during the period from February 1942 to March 1943.

Report discussing experiments on the photometric determination of various elements in the presence of trace amounts of Uranium.

Report detailing the approximate calculation of the neutron flux from a plane source in an infinite medium.

This report describes the flow meter for measuring air-flow rate through special hoods that allow the decrease in flow rate.

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

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.

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."

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."

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."

"Five new dissolution processes for uranium tetrafluoride are discussed-the NH4OH-H2O2 method, the H2SC4 - (NH4)2S2O8 method, the AlCl3 method, the NaAlcl method, and the Al (NO3)3.9E2O method. It is concluded that NaAlCl4 and Al(NO3)3.9H2O are preferable to the other agents, especially with regard to rate of dissolution and ease of manipulation."

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.

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

From summary: "Petrographic, X-ray, and analytical studies were made on synthetic and natural zirconium minerals containing varying amounts of hafnium."