Abstract: "Aluminum-clad nickel-plated uranium is corrosion resistant in boiling water. Samples with intentional defects in the aluminum-nickel clodding layers, after testing for more than 300 hr. showed no sign of rapid failure. The study of electroplated metals on uranium for aluminum cladding has defined the effects of several processing variables on the corrosion resistance. The quality of the uranium and the quality of the aluminum-nickel bond were important. Heat treatment and vacuum outgassing of the nickel-plated uranium prior to aluminum cladding were beneficial, and minimizing the amount of air present in the hot-press assembly was desirable. Variation in the steps for electroplating on uranium did not affect the corrosion resistance of aluminum-clad uranium."

From abstract: Detailed information is given on the theory, design, parts specifications and assembly data for a new radiation detector for measurement of ionizing radiations.

Report discussing the progress of research projects at Battelle Memorial Institute relating to civilian applications during August 1956.

This report follows a preliminary study on uranium migration in pressed and sintered UO2-bearing bodies based on MoSi2 or Al2O3.

Technical report surveying radio-chemical analyses by ORNL's Analytical Chemistry Division and Health-Physics Division of large volumes of rainwater for plutonium, uranium, and fission products. Overall, carrying efficiencies for Al(OH)3 scavenging of rainwater were determined for these elements, as well as for Pu and U. [From Abstract, Introduction]

Summary: A survey was made of KAPL personnel currently exposed to radiation relating to their previous work with radiation or radioactive materials.

Abstract: The sandstones and conglomerates contained in the Shinarump conglomerate stratigraphic level in the area along Colorado River between the Moab and Dewey bridges have been assigned to the lower Chinle. One small anomaly was located, but no favorable radioactive areas were found. Gray-green mudstone and siltstone zones and carbonated material are absent.

Abstract: Uranium was discovered in the Gas Hills of the Wind River Basin by Mr. Nail E. McNeice of Riverton, Wyoming while he was prospecting with a Geiger counter in September 1953. Field parties of the Atomic Energy Commission started work in the area in October 1953.

Report discussing the results of Project "A," which had three main components: "Effect of P2O3 Concentration on the Distribution Coefficient for Uranium Between Crude Phosphoric Acid and O.P.P.A.," "Effect of Chloride Concentration in Phosphoric Acid on the Distribution Coefficient for Uranium Between O.P.P.A. and Phosphoric Acid," and "The Use of Di-Isobutyl Carbinol in the Preparation of a Solvent to Extract Uranium from Phosphoric Acid (N.P.P.A.)."

This report covers an investigation meant to find the feasibility of producing corrosion resistant zirconium from sponge by special melting techniques. The zirconium metal has certain required specifications, such as: the metal must be free from bafnium, and it must be free from other impurities of undesirable neutron cross section.

"This memorandum is a survey of the properties of [U-Bi] reactors for U235 as a fuel and U233 as a fuel using a larger density for the graphite [for calculations]. This will include properties of the core and various reflectors which will be useful for large machine calculations of reflector savings, fast and thermal fluxes, and quantities of interest based on two-group calculations."

Report discussing statistical quality control for the period of December, 1951-February, 1952. Statistical quality control is provided for studies of the General Ionic Analyses Laboratory, the HR Control Laboratory, and the X-10 Laboratories.

Introduction: "Since it has been found that zirconium and zirconium-tin alloys may be embrittled by certain heat treatments, it was decided to determine if welding of these materials affects their ductility in any way. A single bend test in both the longitudinal and transverse directions was used for evaluation of the variables considered."

Discussing an examination of the J.R. Simplot claims in Happy and Hatch Canyons.

A problem proposed by E. Hart to determine whether there are locally high or low neutron densities at the corners of a cubical cavity in a graphite lattice. To simplify the computations consider an infinite two dimensional lattice with a square cavity that has a point source of neutrons at the center (see Figure 1).

The free streaming of neutrons in a cylindrical cavity is investigated. Using experimental data for the flux distribution along the walls, the direct beam hole loss and leakage into the target from the lattice is estimated for the MTA system.

Two xenon extraction runs were made this month. It appears that a small design change in Trap #2 will be necessary so that a dry ice-trichloroethylene slurry can be used for coolant rather than liquid freon. For each of the runs this month the enriched generator was exposed for four hours in the est pile operating at 100 watts. A period of eight hours for cooling and xenon builidup was allowed before the collection and separation runs were started.

In obtaining the results reported here a double focusing magnetic type spectrometer was used. Momentum spread was about 1%, and in most cases 2560 counts per point were taken. An end window Geiger tube was used as a detector. The window was of mica with areal density of 1.6 mg/cm2.

Various organizations in the Biophysics Section of the Radiological Sciences Department participated in evaluating local radioactive particle fallout as influenced by the nuclear explosions at the Nevada Proving Grounds during the early part of 1953. Data collected from approximately 50 air monitoring stations operated by the Regional Survey forces were used to determine the trend of radioactive particle concentrations in the atmosphere between March and June. These measurements were supplemented with the findings of associated organizations in the Biophysics Section during and immediately after the peak influx on May 26.

Abstract : Methods for the chemical separation of strontium, barium, cesium, cerium, yttrium, zirconium, niobium, and tungsten from complex matrices are described. Procedures for the radiometric determination of the longer-lived isotopes of these elements are outlined. Inert carriers are added and the sample is dissolved by fusion with sodium carbonate. The melt is leached first with water and then with hydrochloric acid. The elements are recovered from these fractions by a series of wet chemical and ion exchange procedures, and gravimetric and radiometric determinations performed.

The investigation to be described in this paper was one of several undertaken to resolve a curious discrepancy that had arisen in measurements of the diffusion length of graphite. Those diffusion lengths measured with the graphite layups of 100 Area piles were three to six centimeters higher than the value obtained with the Hanford Standard Pile. The fact that the 100 Area structures of the order of 40 ft. X 40 ft. X 30 ft, not including reflector, approximated an infinite medium, whereas sigma piles are of the order of 8 ft. X 8ft. X 10 ft., suggested the possibility that the diffusion length obtained by mensuration of relative fluxes and application of the conventional equations depended in some way on the size of the medium. Therefore, in order to determine if such a dependency actually exists, it was proposed to erect a series of graphite stacks of different dimensions and to make diffusion length measurements in each.

The purpose of this manual is to present available data which can be used to determine disintegration rates of radioactive samples from counting rates measured under given circumstances with routinely used laboratory instruments. There is also brief discussion on the methods by which the various factors have been determined with reference to the accuracy with which they are known and to what extent the finally quoted disintegration rate is affected by these errors. Emphasis has been placed on those isotopes of particular interest to Radiological Sciences programs and the manual is intended as a standard through the use of which comparable values can be reported from all units in the Department.

From summary: "This report was prepared for the Advisory Committee on Reactor Safeguards for their review and consideration of the potential hazards concerning the Battelle Memorial Institute Research Reactor."

Report documenting the ongoing research and developments of the Oak Ridge National Laboratory's Homogeneous Reactor Project.