Reactor Technology Quarterly Report (open access)

Reactor Technology Quarterly Report

Introduction: The experimental work reported here was undertaken as a part of the over-all design and development program for a nuclear reactor pressure vessel.
Date: April 1958
Creator: unknown
Object Type: Report
System: The UNT Digital Library
OMRE Fuel Removal and Shipping Equipment (open access)

OMRE Fuel Removal and Shipping Equipment

Abstract: A portable assembly for handling and shipping OMRE fuel elements is described and details of its operation are given. Problems of heat transfer and radiation shielding are discussed, and detailed analysis are presented.
Date: April 1, 1960
Creator: Mallon, P. J.; Duncan, D. S. & Noyes, R. C.
Object Type: Report
System: The UNT Digital Library
SRE Mark II Fuel Handling Machine (open access)

SRE Mark II Fuel Handling Machine

Abstract: The Sodium Reactor Experiment Mark II Fuel Handling Machine has been modified to ensure fuel and gas containment during core III operation. A new fuel control system has been designed for the fuel handling machine.
Date: April 20, 1965
Creator: Dietz, H. B.
Object Type: Report
System: The UNT Digital Library
Radiation Effects, Quarterly Progress Report, July - September, 1953 (open access)

Radiation Effects, Quarterly Progress Report, July - September, 1953

None
Date: April 15, 1954
Creator: Faris, F. E.
Object Type: Report
System: The UNT Digital Library
Effect of Reactor Irradiation on the Thermal Conductivity of Uranium Impregnated Graphite at Elevated Temperatures (open access)

Effect of Reactor Irradiation on the Thermal Conductivity of Uranium Impregnated Graphite at Elevated Temperatures

"An experiment to determine the effect of reactor irradiation on the thermal conductivity of uranium-impregnated graphite at elevated temperatures as described. The results show a decrease in the thermal conductivity saturating at [approximately] 60 percent at a temperature of 700 degrees C; at [approximately] 50 percent at a temperature of 1000 degrees C; and at [approximately] 25 percent at a temperature of 1300 degrees C. It was found that after irradiation at a given temperature, exposure at a higher temperature resulted in an increase in the thermal conductivity. The converse was also observed. Within the precision of measurement there was no difference in effed between temperature changes produced by varying the fission rate in the samples and changes produced by varying the power in an external heater."
Date: April 29, 1954
Creator: Durand, Richard E.; Klein, David J. & Nykiel, Harry H.
Object Type: Report
System: The UNT Digital Library
Survey of Processing Methods for the Production of Thorium Metal from Monazite Sand and Thorium Nitrate (open access)

Survey of Processing Methods for the Production of Thorium Metal from Monazite Sand and Thorium Nitrate

Cost estimates for two types of Th producing plants are offered. One utilizes Th(NO3)4 as raw material, the other uses monazite sand. Final processing schemes and plant designs are not fixed, so the estimates represent maximum costs. Recommendations for research and development of Th producing methods are given.
Date: April 23, 1951
Creator: Bulkowski, H. Harold & Maerker, John B.
Object Type: Report
System: The UNT Digital Library
The Inference of Adsorption from Differential Double Layer Capacitance Measurements (open access)

The Inference of Adsorption from Differential Double Layer Capacitance Measurements

From Abstract : "Dependence of boundary tension and capacitance at the mercury-aqueous 0.1 N HClO4 interface on polarization and organic solute concentration were determined for the colutes n-amyl alcohol and phenol. ... An earlier treatment proposed by this Laboratory based on a (non-thermodynamic) assumption of linear variation of surface charge density with coverage appears adequately justified for inference of fractional surface coverages near the electrocapillary maximum, but must be considered approximate for evaluation of molar area at full coverage in cases where linear variation of charge with coverage has not been demonstrated."
Date: April 26, 1963
Creator: Hansen, Robert S.; Kelsh, Dennis J. & Grantham, D. H.
Object Type: Report
System: The UNT Digital Library
The Effect of Age on the Radiosensitivity of Mice (open access)

The Effect of Age on the Radiosensitivity of Mice

Abstract: Mice of different ages ranging from 1.5 to 12 months have been exposed to gamma rays in an effort to determine the change in radiosensitivity with age. The dose necessary to cause 50% killing was determined for each age group and sex. No change in sensitivity with age was observed with either sex, although the experimental error in the case of the males was quite large. The females were found to be more resistant than the males.
Date: April 8, 1946
Creator: Curtis, H. J.; Zirkle, Raymond E. (Raymond Elliot), 1902-1988; Anderson, Ernest C., 1920-2013 & Riley, E. F.
Object Type: Report
System: The UNT Digital Library
The Acute Radiotoxicity of Injected Na²⁴ for Mice and Rats (open access)

The Acute Radiotoxicity of Injected Na²⁴ for Mice and Rats

The following report describes the results from studies based on the toxicity and metabolism of radioactive substances derived from uranium fission. Rats and mice were administered radioactive sodium and reactions and changes were studied.
Date: April 15, 1948
Creator: Finkle, R. D.; Snyder, R. H.; Kisieleski, Walter E.; Teresi, J.; Broido, A. & Tompkins, P. C.
Object Type: Report
System: The UNT Digital Library
Remote Control Apparatus (open access)

Remote Control Apparatus

Report discussing equipment that can be used to perform chemical and mechanical operations involving radioactive materials safely. Illustrations of the equipment are provided.
Date: April 12, 1948
Creator: Goertz, R. C.
Object Type: Report
System: The UNT Digital Library
Feasibility Investigation of a Closed Cycle Boiling Water Reactor for the Propulsion of a Merchant Ship (open access)

Feasibility Investigation of a Closed Cycle Boiling Water Reactor for the Propulsion of a Merchant Ship

Summary: The scope and intent of this report is to demonstrate the feasibility of a nuclear powered tanker for service in the United States Maritime Fleet.
Date: April 8, 1957
Creator: unknown
Object Type: Report
System: The UNT Digital Library
A Report on the Interaction of the Nuclear and Power Plant Controls for the SRE Steam Electric Generating Station (open access)

A Report on the Interaction of the Nuclear and Power Plant Controls for the SRE Steam Electric Generating Station

Introduction: The purpose of this report is to describe in further detail the control systems that interconnect the SRE with the steam plant.
Date: April 30, 1956
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Critical Path Scheduling in Maintenance (open access)

Critical Path Scheduling in Maintenance

Summary: The following narrative interspersed with figures and attached reference exhibits is designed to acquaint the reader with the scheduling procedure developed at ORGDP, trial results and evaluation, subsequent improvement, further application, and use in conjunction with our IBM 7090 Computer.
Date: April 10, 1961
Creator: Gritzner, C. L.; Jones, J. P. & Ellis, J. M.
Object Type: Report
System: The UNT Digital Library
Recovery of Uranium From Contaminated Precipitron Oil (open access)

Recovery of Uranium From Contaminated Precipitron Oil

Abstract: The distillation and residue extraction recovery procedures developed for the recovery of uranium from Kinney and diffusion pump oil, were applied to contaminated precipitron oil. The effectiveness and advisability of using the method, in whole or in part, is discussed, and various recommendations for processing this particular type of oil are presented. Additional contaminating substances present in this type of oil added to the complexity of the problem but a satisfactory recovery procedure was, nevertheless, successfully developed.
Date: April 17, 1947
Creator: Lee, J. E.; Aikin, L. M. & Susano, C. D.
Object Type: Report
System: The UNT Digital Library
Resonance Absorption of Thorium (open access)

Resonance Absorption of Thorium

Abstract: Cadmium ratios for very thin (neutron and beta-wise) foils of thorium, gold, vanadium and indium have been measured in the glory hole of the WBNS. These cadmium ratios, together with the known thermal cross sections and a given calculated resonance integral for gold, were used to evaluare the resonance integrals of thorium, vanadium, and indium.
Date: April 2, 1953
Creator: Martin, D. H.
Object Type: Report
System: The UNT Digital Library
The Detection of Small Amounts of Fluorine in Large Amounts of Chlorine (open access)

The Detection of Small Amounts of Fluorine in Large Amounts of Chlorine

Abstract: "Tests have been developed for both the qualitative detection and quantitative determination of fluorine in chlorine. The qualitative test is made by passing the gas through manganous chloride. If the pink solid tubes brown there is greater than 0.5 percent of fluorine in the gas. The quantitative test is a modification of the Steiger and Marvin Test with oxidized titanium solution."
Date: April 1, 1946
Creator: Lafferty, Robert H., Jr. & Winget, Rasho
Object Type: Report
System: The UNT Digital Library
A Mathematical Analysis of the Calutron (open access)

A Mathematical Analysis of the Calutron

Abstract: "The definitions of the fundamental measures of calutron operation including enhancement, current ratio, and process efficiency are set forth with derivations of the relationships between them. An analysis of the plant process is carried out for both the tanks limited and the charge limited case. Equations are derived for plant X output and plant X utilization efficiency. Effective production is defined and the value of increment to a mass of product material in terms of effective production is determined. An equation giving the X concentration below which product material should be reprocessed is derived."
Date: April 12, 1946
Creator: Leith, C. E.
Object Type: Report
System: The UNT Digital Library
Dissolution and Recovery of Uranium from Phosphate Rock and Shale by Chemical Methods (open access)

Dissolution and Recovery of Uranium from Phosphate Rock and Shale by Chemical Methods

The following report briefly covers broad general features of the chemical studies to be used by the Atomic Energy Commission in considering future work on the chemical studies of phosphate rock and shale.
Date: April 7, 1947
Creator: Sullivan, John D.
Object Type: Report
System: The UNT Digital Library
Uranium Hydride : A Survey (open access)

Uranium Hydride : A Survey

The following report discusses the results of a survey that was initiated to ascertain the availability of uranium hydride in tonnage quantities.
Date: April 10, 1950
Creator: Kitzes, A. S.
Object Type: Report
System: The UNT Digital Library
Mound Laboratory Liquid Waste Disposal Research Quarterly Report for January - March, 1950 (open access)

Mound Laboratory Liquid Waste Disposal Research Quarterly Report for January - March, 1950

The following report follows a complete radiochemical analysis that has been made on the sample of first-cycle neutralized waste, as well as a gravimetric analysis made on the sludge in the sample of first-cycle waste.
Date: April 1, 1950
Creator: Monsanto Chemical Company
Object Type: Report
System: The UNT Digital Library
Separation of Tuballoy From Gunk Solutions by Sulfite Precipitation (open access)

Separation of Tuballoy From Gunk Solutions by Sulfite Precipitation

Summary: A method is presented for the precipitation of tuballoy, apparently as a tubanyl ammonium sulfite, from gunk solutions containing the contaminants encountered in the recovery cycle. The impurities are not precipitated under the conditions employed, and their amounts in the product are reduced to values which can be attributed to occlusion. The recovery of tuballoy on one precipitation ranges from 99.5% to 99.9%.
Date: April 18, 1945
Creator: Ryon, A. D. & Armstrong, E. C.
Object Type: Report
System: The UNT Digital Library
15 MW Gas-Cooled Closed-Cycle Reactor Power System Study: Final Report, Volumes 1-2 (open access)

15 MW Gas-Cooled Closed-Cycle Reactor Power System Study: Final Report, Volumes 1-2

This report covers a feasibility study for a 15 megawatt gas cooled reactor power system, conducted by the Ford Instrument Company Division of the Sperry Rand Corporation during the months of March to August 1956.
Date: April 1, 1957
Creator: Ford Instrument Company
Object Type: Report
System: The UNT Digital Library
Corrosion of Zircaloy in Crevices under Nucleate Boiling Conditions (open access)

Corrosion of Zircaloy in Crevices under Nucleate Boiling Conditions

Abstract: The MSAR corrosion test loop was used to study the effect of VKE-shaped crevices on the corrosion resistance of Zircaloy under boiling heat-transfer condtions in both ammoniated and lithiated water at pH 10.5.
Date: April 1962
Creator: Anderson, W. Kermit & McGoff, M. J.
Object Type: Report
System: The UNT Digital Library
Mechanical Properties of Zircaloy-2 Weld Metal (open access)

Mechanical Properties of Zircaloy-2 Weld Metal

Abstract: Zircaloy-2 weld metal, obtained by inert gas non-consumable-electrode welding, was subjected to tensile, strain fatigue, and creep-rupture testing.
Date: April 15, 1961
Creator: Beitscher, S.
Object Type: Report
System: The UNT Digital Library