Separation of Americium From Lanthanum by Fractional Oxalate Precipitation From Homogeneous Solution (open access)

Separation of Americium From Lanthanum by Fractional Oxalate Precipitation From Homogeneous Solution

Report discussing a study in which "a separation of americum from americum-lanthanum mixtures is obtained by the fractional precipitation of dilanthanum trioxalate from homogeneous solution."
Date: October 1953
Creator: Hermann, John A.
System: The UNT Digital Library
Variation of Critical Parameters Between U-235 Assays of 4.9 Percent and 93.5 Percent (open access)

Variation of Critical Parameters Between U-235 Assays of 4.9 Percent and 93.5 Percent

The following report uses empirical relations and the elementary diffusion theory transformation, the EDIT, to predict some of the minimum critical values of the various parameters of interest with reasonable accuracy. This document reports the minimal critical mass, volume, and cylinder diameter for uranium of 4.9% assay.
Date: October 23, 1953
Creator: Henry, Hugh F. & Newlon, C. E.
System: The UNT Digital Library
A Continuous Gamma Activity Monitor for the Product Stream of the Uranium Recovery Plant (open access)

A Continuous Gamma Activity Monitor for the Product Stream of the Uranium Recovery Plant

A continuous gamma-monitoring instrument capable of measuring the activity of the product of the Uranium Recovery plant has been developed and applied under process conditions. It has a detection limit of 15% and a normal range of up 1000% of the activity of natural uranium. Activity measurements made with this instrument have shown good correlation with laboratory determinations and are contributing to improved control of the solvent extraction process.
Date: October 1, 1953
Creator: Leboeuf, M. B.; Connally, R. E. & Upson, U. L.
System: The UNT Digital Library
Microtitration of Free Acid in Uranyl Nitrate Solutions (open access)

Microtitration of Free Acid in Uranyl Nitrate Solutions

The approaches to the solution of the problem of removing or nullifying the effect of the hydrolysis of uranyl ion on acid titrations were: 1) use of a complexing agent and titration technique suitable for micro samples; 2) addition of a reagent that reacts with uranium to release 1 or 2 equivalents of acid per mole of uranium present (this permits correcting the titration value for the acid contributed by the uranium, or conversely permits an alkimetric titration of uranium); 3) separation of the uranium and acid with subsequent titration of the acid; and 4) direct titration of the sample with base. All these approaches yielded at least one method suitable for titrating acid in micro samples of uranium nitrate solutions.
Date: October 1, 1953
Creator: Carson, W. N., Jr.
System: The UNT Digital Library
Radiological Sciences Department:  Quarterly Progress Report, Research and Development Activities, July-September, 1953 (open access)

Radiological Sciences Department: Quarterly Progress Report, Research and Development Activities, July-September, 1953

This is the sixteenth quarterly report of the research and development activities of the Radiological Sciences Department, Hanford Atomic Products Operation, as before, includes some items charged to control but included for general interest. Such are identified as "not charged to research."
Date: October 2, 1953
Creator: Parker, H. M.
System: The UNT Digital Library
Analysis of Errors to be Expected in Measuring the Neutron Absorption Cross Section of C-12 (open access)

Analysis of Errors to be Expected in Measuring the Neutron Absorption Cross Section of C-12

An experiment now in progress should give some accurate information about the thermal neutron absorption cross section of carbon 12. This report outlines and summarizes this experiment and analyzes it to determine the main sources of error and the probably error in the final result.
Date: October 7, 1953
Creator: Seppi, E. J.
System: The UNT Digital Library
Thermocouples and Cables for Nuclear Reactors (open access)

Thermocouples and Cables for Nuclear Reactors

From abstract: "The development, design, specification, and manufacture of special-purpose thermocouples sheathed in stainless steel for use in nuclear reactors are described. In connection with this work, a three element cable for transmitting the signal from neutron-flux measuring devices was developed."
Date: October 1953
Creator: Stone, J. M.
System: The UNT Digital Library
Use of Commercial Grade Methane in ASP Counting Instruments (open access)

Use of Commercial Grade Methane in ASP Counting Instruments

The gas commonly used in the chamber of the Simpson Proportional Alpha Counter (ASP) is the high grade, 99% pure methane. The cost of the gas has often raised the question of finding an adequate substitute and a number of substitutions have been attempted. Commercial methane has been substituted successfully for 99% pure methane and its use is recommended in ASP counters. Neither commercial nor technical methane caused any significant changes in instrument operation.
Date: October 8, 1953
Creator: Rasmussen, M. J.
System: The UNT Digital Library
The Less Familiar Elements in the Atomic Energy Program (open access)

The Less Familiar Elements in the Atomic Energy Program

Many factors are responsible for the rapid growth of analytical chemistry during the past ten to fifteen years. One of the most important of these factors is the greatly increased significance to present day chemistry of many elements that in the recent past were principally chemical curiosities. Since the Atomic Energy program is concerned with many such elements, it is of interest to discuss the cause for this concern and the resulting effect on the field of analytical chemistry. A number of pertinent analytical research problems at Hanford will be cited as examples.
Date: October 12, 1953
Creator: Bushey, A. H.
System: The UNT Digital Library
Laboratory Corrosion Tests of Spring Steel Wire in Simulated Neutralized Purex Process Waste Solution (open access)

Laboratory Corrosion Tests of Spring Steel Wire in Simulated Neutralized Purex Process Waste Solution

The purpose of the short duration corrosion test was to obtain preliminary data regarding the corrosion resistance of the spring steel wire in Purex process waste solutions and to measure any changes in the tensile properties of the wire resulting from this exposure.
Date: October 16, 1953
Creator: Endow, N.
System: The UNT Digital Library
Separation of Azeotropes by Means of Diffusion through Porous Membranes (open access)

Separation of Azeotropes by Means of Diffusion through Porous Membranes

Thesis discussing experiments to separate azeotropes into pure components testing eleven minimum boiling point azeotropic systems: (1) acetone-methanol, (2) carbon tetrachloride-ethyl acetate, (3) cyclohexane-ethanol, (4) benzene-isopropanol, (5) benzene-n-propanol, (6) benzene-cyclohexane, (7) benzene-methanol, (8) benzene-ethanol, (9) acetone-carbon, (10) isopropoanol-water, and (11) ethanol-water.
Date: October 1953
Creator: Hagerbaumer, Donald H. & Kammermeyer, Karl
System: The UNT Digital Library
Practical Reactor Theory (open access)

Practical Reactor Theory

Derivation and basic formulas the physicist or nuclear engineer needs to do the necessary nuclear calculation for a reactor design.
Date: October 21, 1953
Creator: Webster, J. W.
System: The UNT Digital Library
Operation and Maintenance Instructions for Gamma Scintillation Monitor - Model 3 (open access)

Operation and Maintenance Instructions for Gamma Scintillation Monitor - Model 3

Gamma scintillation monitor Model 3 is designed to continuously monitor and record the gamma activity of a process solution.
Date: October 1, 1953
Creator: Connally, R. E.
System: The UNT Digital Library
Supplementary Report , Anomaly No. 30 F, Miller Hill Area, Carbon County, Wyoming (open access)

Supplementary Report , Anomaly No. 30 F, Miller Hill Area, Carbon County, Wyoming

Discussing an anomaly discovered by airborne methods.
Date: October 12, 1953
Creator: Magleby, Dan N. & Mallory, Neil S.
System: The UNT Digital Library
Progress Report on the Flotation of Uranium Bearing Minerals From Lake Athabaska Ore, Sample 43-1 (open access)

Progress Report on the Flotation of Uranium Bearing Minerals From Lake Athabaska Ore, Sample 43-1

At the request of the Atomic Energy Commission, a 456 pound sample of Lake Athabaska ore was shipped to this laboratory by the Radioactivity Division of the Canadian Bureau of Mines. The sample was received on March 10, 1952 and given our number 43-1. Several series of flotation tests were performed on the sample.
Date: October 12, 1953
Creator: Breymann, John B.; Charles, W. D. & Thomas, P. N.
System: The UNT Digital Library