Evaluation of Properties of Irradiated Zircaloy-2 Pressure Tube from KER Loop 1 (open access)

Evaluation of Properties of Irradiated Zircaloy-2 Pressure Tube from KER Loop 1

Report describing the evaluation of the effects of irradiation on a high pressure water loop that ruptured while testing fuel elements. Includes photographs of the damaged tube as well as chemical analyses.
Date: December 1962
Creator: Defferdin, L. J.
System: The UNT Digital Library
A Device for Recording Fuel Element Dimension on Punched Paper Tape (open access)

A Device for Recording Fuel Element Dimension on Punched Paper Tape

Report that "describes a system for translating the position of a strip-chart recorder potentiometer shaft into decimal digital form" (p. ii).
Date: December 1962
Creator: Driver, G. E.
System: The UNT Digital Library
Economic Evaluation of a 300 Mwe Fast Supercritical Pressure Power Reactor (open access)

Economic Evaluation of a 300 Mwe Fast Supercritical Pressure Power Reactor

Report regarding Hanford Laboratories' 300 Mwe fast supercritical pressure power reactor. This includes descriptions of the plant and reactor, their operations, safety systems, and plant economics. Appendices begin on page 107.
Date: December 9, 1963
Creator: Aase, D. T.; Fox, J. C.; Hennig, R. J.; Peterson, R. E.; Stewart, S. L. & Toyoda, K. G.
System: The UNT Digital Library
In-Reactor Monitoring of Zircaloy-2 Plutonium Recycle Test Reactor Pressure Tubes: Part 3, July 1963 - November 1963 (open access)

In-Reactor Monitoring of Zircaloy-2 Plutonium Recycle Test Reactor Pressure Tubes: Part 3, July 1963 - November 1963

Report containing the results of a two year program wherein the 85 zircaloy-2 pressure tubes in Hanford Laboratories' Plutonium Recycle Test Reactor (PRTR) were monitored. Experimental procedures and results are described.
Date: December 1963
Creator: Pankaskie, P. J.
System: The UNT Digital Library
Quarterly Progress Report Metallurgy Research Operation: July, August, September, 1963 (open access)

Quarterly Progress Report Metallurgy Research Operation: July, August, September, 1963

Quarterly progress report metallurgy research operation at Hanford Atomic Products Operation in Richland, Washington.
Date: December 30, 1963
Creator: unknown
System: The UNT Digital Library
The Effect of Temperature on the Neutron Attenuation of Magnetite Concrete (open access)

The Effect of Temperature on the Neutron Attenuation of Magnetite Concrete

Comparison of experimentally determined relaxation lengths to the value calculated from the concrete composition.
Date: December 11, 1958
Creator: Wood, D. E.
System: The UNT Digital Library
Trans-Plutonium Isotope Buildup by Neutron Irradiation of Plutonium (open access)

Trans-Plutonium Isotope Buildup by Neutron Irradiation of Plutonium

Graphs for estimation of plutonium and trans-plutonium isotopic content of irradiated plutonium reactor fuel of various initial isotopic compositions.
Date: December 15, 1958
Creator: Brauer, F. P. & Burley, Helen H.
System: The UNT Digital Library
Decontamination of Redox Feed Solutions by Super Filtrol Scavenging (open access)

Decontamination of Redox Feed Solutions by Super Filtrol Scavenging

From introduction: "This report examines the hazard which would result in the extremely unlikely event that all of the safety devices failed to operate either by accident or sabotage."
Date: December 2, 1949
Creator: Roake, W. E. & Hick, H. G.
System: The UNT Digital Library
Freezing Point Data for UNH-H₂O-HNO₃ Systems (open access)

Freezing Point Data for UNH-H₂O-HNO₃ Systems

The following report follows a series of experiments on the freezing points of 25 UN-H2O-HNO3 solutions.
Date: December 17, 1947
Creator: Harmon, M. K.
System: The UNT Digital Library
Effect of Heat Treatment of the Structure and Hardness of Gamma Extruded Uranium : Final Report, Problem Assignment 2-M (open access)

Effect of Heat Treatment of the Structure and Hardness of Gamma Extruded Uranium : Final Report, Problem Assignment 2-M

The following document is an interim report on studies made to determine the optimum time-temperature treatment to produce a recrystallized grain structure in gamma extruded uranium."
Date: December 24, 1947
Creator: Padden, R. M.
System: The UNT Digital Library
Neutralization of HNO₃ in Redox ICU an IAW Streams (open access)

Neutralization of HNO₃ in Redox ICU an IAW Streams

The following memorandum outlines the procedures used on the neutralization of HNO3 in redox ICU and IAW streams, and the factors influencing their choice. The procedures involve a) hexone removal by evaporation in the presence of a retardant, b) destruction of the retardant, c) nitric acid elimination by boiling with aluminum and d) concentration of the remaining solution by evaporation.
Date: December 10, 1948
Creator: Curtis, M. H.
System: The UNT Digital Library
Initial Investigation of the Mechanical Properties of Uranium at Elevated Temperatures (open access)

Initial Investigation of the Mechanical Properties of Uranium at Elevated Temperatures

Introduction: "Knowledge of the mechanical properties of uranium at elevated temperature is essential in order to understand and predict the fabrication characteristics and pile behavior of this metal. This report presents the experimental data obtained from beta heat-treated specimens which were originally machined from one production, alpha-rolled uranium rod."
Date: December 2, 1952
Creator: Hueschen, R. E. & Pitt, C. H.
System: The UNT Digital Library
X-ray Photometric Assay of Plutonium in Metal Castings (open access)

X-ray Photometric Assay of Plutonium in Metal Castings

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.
Date: December 12, 1952
Creator: Lambert, M. C.
System: The UNT Digital Library
Nitration Reactions of Shell Spray Base under Purex Waste Recovery Process Conditions (open access)

Nitration Reactions of Shell Spray Base under Purex Waste Recovery Process Conditions

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."
Date: December 5, 1952
Creator: Wagner, R. M.
System: The UNT Digital Library
Use of the Boiler Neutron Source for Exponential Experiments (open access)

Use of the Boiler Neutron Source for Exponential Experiments

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.
Date: December 11, 1952
Creator: Davenport, D. E.
System: The UNT Digital Library
Production of UO₃ by Calcination of Uranyl Peroxide (open access)

Production of UO₃ by Calcination of Uranyl Peroxide

This report discusses the calcination or heating of UO₃. When UO₃ is heated, it loses ionic impurities and can produce uranyl peroxide.
Date: December 10, 1952
Creator: Moore, R. L. & Watts, R. A., Jr.
System: The UNT Digital Library
Heavy Aggregate Investigation (open access)

Heavy Aggregate Investigation

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.
Date: December 19, 1952
Creator: Brown, R. E.
System: The UNT Digital Library
Applied Potential Corrosion of Aluminum : Final Report (open access)

Applied Potential Corrosion of Aluminum : Final Report

Report describing data resulting from dynamic tests to determine applied potential corrosion of aluminum.
Date: December 5, 1955
Creator: Sanborn, Kenneth L.
System: The UNT Digital Library
Remotely Operated Irradiation Facility : (Sample Carrier) (open access)

Remotely Operated Irradiation Facility : (Sample Carrier)

Report discussing a possible solution for providing a remotely operated way of handling samples at an irradiation facility. Explanation of operating requirements, equipment, and a possible layout is included.
Date: December 8, 1955
Creator: Fox, J. C.
System: The UNT Digital Library
Test of Water Quality Velocity on Pitting of 72-S Aluminum (open access)

Test of Water Quality Velocity on Pitting of 72-S Aluminum

Report discussing a test aimed at determining if high velocity water could cause severe pitting in 72-S aluminum. This test was designed after an increase in the amount of pitting-caused water leaks in reactors.
Date: December 8, 1955
Creator: Houck, William C.
System: The UNT Digital Library
Experimental Rolling of Uranium : Lackawanna No. 3 (open access)

Experimental Rolling of Uranium : Lackawanna No. 3

The following report is one of a series of rolling tests to establish the rolling process for Feed Materials Production Center at Fernold, Ohio. The primary objective of this program is to find a mechanically feasible process for continuous rolling of uranium.
Date: December 13, 1951
Creator: Riches, J. W.
System: The UNT Digital Library
The Valve-Actuated Pulse Column Design and Operation (open access)

The Valve-Actuated Pulse Column Design and Operation

The following report describes a countercurrent extraction column, which employs timed solenoid valves and pressurized feeds to provide a pulsing action to disperse the phases. This report further describes the 4-stage cycle of the column operation.
Date: December 3, 1951
Creator: Burger, L. L.
System: The UNT Digital Library
Physical Properties of the System Uranyl Nitrate - Aluminum Nitrate - Nitric Acid - Water - Hexone: Part 6. Distribution Coefficients of Plutonium(IV) Nitrate (open access)

Physical Properties of the System Uranyl Nitrate - Aluminum Nitrate - Nitric Acid - Water - Hexone: Part 6. Distribution Coefficients of Plutonium(IV) Nitrate

Report discussing the properties of plutonium and plutonium's distribution between hexone and aqueous phases, which relates to the function of Redox plants
Date: December 1, 1950
Creator: Groot, C.; Rehn, I. M. & Slansky, C. M.
System: The UNT Digital Library
Corrosion of Stainless Steel Type 309SCB in 200 Area Dissolver Solution Containing Mercuric Ion (open access)

Corrosion of Stainless Steel Type 309SCB in 200 Area Dissolver Solution Containing Mercuric Ion

The following report provides data from corrosion tests meant to evaluate the performance of Type 3098Cb stainless steel in BiP04 process dissolver solution containing mercuric ion.
Date: December 20, 1951
Creator: Sanborn, K. L.
System: The UNT Digital Library