Summary: A method for the separation of cesium from macro quantities of sodium and potassium using an ion exchange resin, Dowex 50, has been developed. A 95% recovery of cesium with a reduction of the solid content of 95% was found possible. Curves illustrating the effect of acidity, column length, and flow rate are presented in the report. The sodium form, hydrogen form and ammonium form of Dowex 50 were investigated; the hydrogen form was found to give the best separation.

Abstract: The thermal distortion of a Y-shaped hafnium control rod heated by arrays of individually controlled radiation heaters was studied. The large axial and radial temperature gradients specified for this control rod were easily obtained with the radiation-heating method. The distortion, as measured with dial indicators, amounted to a 2-mil movement of the free end of the rod in the direction of the coolest blade.

Survey of properties of materials which might be suitable for use in various locations in a supercritical-water reactor. Properties examined include tensile strength, rupture strength, endurance strength, Young's modulus, tensile elongation, coefficient of thermal expansion, coefficient of thermal conductivity, density, nominal composition, usual heat treatments and thermal-neutron-absorption cross sections.

Technical report detailing expansion of the Aircraft Nuclear Propulsion at the Oak Ridge National Laboratory. Major facilities completed at this time were the Shielding Rector, the ANP Critical Facility, and the 86-in. Cyclotron. Outlines further need for radiation damage studies. [From Summary]

Technical report and preliminary design calculations describing a type of liquid fuel reactor adaptable for production or breeding on a U-233 cycle based on data at Brookhaven National Laboratory. Describes design calculations for generating significant amounts of power and neutrons by use of uranium-bismuth solutions with fused salts in the reactor system.

Technical report outlining how uranium hexaflouride was prepared be the direct combination of irradiated uranium metal with elemental fluorine and subsequently decontaminated by adsorption, filtration, and sublimation on a laboratory scale. Report proposes a survey of other methods of preparing UF6 from uranium metal, a study of adsorption techniques for removing plutonium from UF6, and an investigation of fractional distillation for removing the volatile fission product fluorides from UF6. [From Abstract, Summary]

The following report investigates the possible use of thermal emf's to produce the plasma-containing magnetic field in a thermonuclear reactor.

From introduction: The Monument No. 2 mine is in the Navajo Indian Reservation, Apache County, Arizona, about 20 miles southwest from the San Juan River at Mexican Hat, Utah, and 26 miles southwest from Mexican Water, Arizona. The property has been operated, since its discovery, by Vanadium Corporation of America, which holds a 10-year mining lease, granted through the Interior Department, to 43 acres of ground. History of the discovery of the deposit is vague, but reportedly it was first seen around 1942 by a Navajo who mentioned the occurrence to Harry Goulding, Indian trader, who in turn advised D. W. Viles of Vanadium Corporation of America. Minor portions of the deposit are held by Cato Sells and Harvey Black, Navajos, under mining permits issued by the Navajo Tribal Council. The Sells acreage is being operated by Climax Uranium Corporation.

Introduction: This document describes the results of a six-week conceptual design study of an organic moderated and cooled reactor (OMCR) power plant adapted to a Class T-7 tanker.

From Abstract: "A literature survey was made of both welding and brazing methods that might be used to minimize the amount of exposed core material and provide the longest path for corrosion in the event of a defective weld in enextruded Zircaloy-2-clad uranium and uranium-2 w/o zirconium fuel elements."

This report discusses the high-velocity collisions of two identical solid plates driven by high explosives. The collision data employs dural, mild steel, brass and lead, as well as experimenting with jetless and jet-forming collisions.

Abstract: "The counting efficiency of Pa²³³ has been determined by comparison of the counting rate of Pa²³³, under stated conditions, with the disintegration rate of U²³³ produced by Pa²³³ decay."

First 31 pages of a quarterly report discussing the progress made on research projects during the period from October 1950 to December 1950. This section of the report discusses progress on studies of the metabolic properties of various elements.

Discussing the petrography of the black Toldilto Limestone Area with respect to the processing properties

To calibrate a pulse height discriminator, the amplitude of the calibrating pulse must be known. If the amplitude is known, the discriminator dial may be calibrated in terms of the input signal required to just trip it. This is the purpose for which the Discriminator Calibrator was designed. It produces pulses of variable but known amplitude with a rep. rate variable from 3 pps to 4000 pps. The main use of this unit at the UCRL is in conjunction with scalers at fixed counting locations.

The use of diffusion theory to attempt to reproduce the chemical data of Hicks and Stevenson for the spatial distribution of neutrons in a solid block of uranium that is bombarded by 190 Mev neutrons is described.

Early in the design of the Mark I accelerator it was decided to install magnetic lenses in the drift tubes. A number of model magnets were constructed and tested to determine the best design for these lenses. This report includes only the results of the tests on the final models of the magnets that are designed for Mark I.

The recent interest in tributyl phosphate as an extracting solvent for uranium indicated that consideration of n-butyl phosphoric acid for this application might be of interest if some way could be devised to overcome the manipulation and miscibility difficulties. It was found that if the material was placed in any one of a number of carrier solvents, it had a remarkably strong extractive effect on uranyl ion out of acid solutions without a salting agent present.

During the canning of slugs for Production Test 313-105-3-M, a high number of rejects were caused by gas voids in the A1-S1 bonding layer. Since the heat treatment of the slugs in a molten salt bath resulted in a chemically altered surface, an investigation was made to determine the volume of gas evolved from salt-bath heat-treated slugs as compared to other types of slugs. This test was designed as a preliminary test to determine if there were a significant differences.

Technical report detailing corrosion tests of Type 347 stainless steel for two weeks in boiling uranyl nitrate, sulfuric acid media, with and without additions of Al+3 and F-1 in a 2:1 mole ratio. The results of these tests show that although the presence of aluminum greatly reduces the deleterious effect of fluoride, the corrosion rates are still three to four times greater than when no fluoride is present. [From Abstract]

From abstract: "An apparatus is described which automatically separates a flow of drops into a series of equal samples."

Air filter and rainwater collections of atmospheric fall-out were made at Atlanta, Georgia; Urbana, Illinois; Topeka, Kansas; Fort Worth, Texas; and Nashville, Tennessee. Collections reflect the effects of the radioactive cloud from the Nevada tests.

APPR-1 is described and the various hazards are reviewed.

From abstract: "The design of a scintillation counter for measuring radioactive contamination of hands and feet is described."