This following report discusses certain topics pertinent to the x-ray photometric method, such as the optimum size of sample and of sample concentration, the technique of measurement for high precision, the use of easily prepared uranium standards for future calibrations and corrections for extraneous substances, and it compares results obtained by both x-ray and chemical assays.

Abstract: "Experiments were performed to characterize the types of nitro compounds that might be formed by reaction of Shell Spray Base with nitric acid, to determine the extent of their formation, if any, and their path under conditions of nitric acid recovery in the Purex Process. It is concluded that the instability of Shell Spray Base to nitration, under conditions to prevail in the plant, presents neither a disposal problem nor a safety problem."

The following report deals with the application of the water boiler neutron source to the exponential experiments in an attempt to speed up lattice testing measurements.

This report discusses the calcination or heating of UO₃. When UO₃ is heated, it loses ionic impurities and can produce uranyl peroxide.

This report follows a manuscript report made in January 11, 1952, and provides results of a survey that gives corrections as well as suggestions for new and local sources of aggregate material in comparison to the original report. These reports were made in response to a heavy desire of improvement in reactor design and shielding.

This report discusses the production of plutonium metal through the reduction of plutonium tetra fluoride with calcium metal and sulfur. It elaborates that iodine, which was originally used instead of calcium metal, presented several practical problems, but reductions completed with calcium were unsatisfactory.

This report examines a uranium slug that has been produced by powder metallurgical methods and exposed in the 100-DR Pile and was deformed during pile exposure.

Report covering an experiment on a method for determining the crystallographic orientation within uranium rods. From summary: "The crystallographic orientation existing in rolled uranium rods may be determined by comparing the diffraction pattern obtained from an unknown specimen with the diffraction pattern obtained from a sample known to be randomly oriented."

Report describing data resulting from dynamic tests to determine applied potential corrosion of aluminum.

The following report provides the results of an accelerated corrosion test that was performed to compare the effect of two coagulants on the corrosion rates of aluminum slug jacket alloy and 72S. Additionally, some analytical data on the water from the two treatments were obtained and are presented in this report.

Summary: "Analysis of the power-level transient following the rapid insertion of a large absorber into an operating pile provides an excellent means of determining the reactivity effect of the absorber . Recent improvements in instrumentation make possible the measurement of the strength of the entire vertical safety rod system of the production units by means of this technique, and rapid calibration of the high-speed control rods by means of this technique, and rapid calibration of the high-speed control rods in the H unit is also feasible. The details of the method are presented together with recent experimental confirmation from the Test Pile of certain features of the theory."

Objective: "Production Test 235-1 and an amendment, were written to outline the procedures for reducing the outgassing time and evaluating the effects of these reductions."

From abstract: "The purpose of this investigation was to establish basic rates of formation of chemical films deposited on aluminum surfaces from water flowing over such surfaces. It was desired to obtain specific information, within certain ranges, as to the influence of temperature, water velocity, and type of aluminum on the rate of film formation."

Report discussing a study on the number of radioactive particles in the atmosphere by Hanford Works. The study's l procedures and results are included.

This report discusses the state of stress caused by pressure in process tubes, elaborating on five "theories of failure" that each explain the stress in process tubes in a different manner. These theories, which are depicted in a graph, include maximum normal stress, maximum strain, maximum shear stress, maximum strain energy, and maximum strain energy of distortion.

Report discussing studies regarding the properties and nuclear constants of xenon, an element relevant to use of high power thermal neutron reactors.

Summary: "The quantity of water adsorbed by graphite at various relative pressures has been determined and the data are presented in graphical and tabular form."

From introduction: "Analytical procedures for the determination of plutonium samples from the extraction and concentration plants utilize the carrying of the hydroxylamine-reduced trivulent plutonium by coprecipitation on lanthanum fluoride. Most other plutonium procedures also take advantage of the efficient carrying on lanthanum fluoride."

From abstract: "The reactivity effects of one and of two highly enriched fuel rods placed into a natural uranium lattice thermal pile are investigated according to the small source model."

Report describing the temperature in the Brookhaven concrete shield proposed for the X reactor. The report details the methods and equations used to find the values that determined that the effect of the gun barrel assembly in cooling the concrete is negligible.

This report discusses a proposed method for treating the effect of increasing critical mass of plutonium solutions, which occurs when hydrogen density is reduced by dilution with heavier nuclei.

Introduction: "The observations reported in this document were obtained by C.H. Pitt during his assignment to the Corrosion Group September through October 1951. The tubes examined were: 1.) 0893-F Discharged for corrosion examination after leaking; 2.) 1488-DR Discharged to determine caused of obstruction; 3.) 2276-D Discharged for corrosion examination; 4.) 2376-D Discharged for corrosion examination; 5.) 1185-H Discharged to evaluate the effect of magnesium front dummies."

From abstract: "The present paper proposes a lattice test pile, (or LTP) as an alternate to the continuing program of building up and tearing down of exponential piles."

The following document describes data collected from a 14-month period of analyzing crustaceans containing radioactivity. Provided is information based on the change of radioactivity through seasonal changes.