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
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
Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: July 1 - September 30, 1963 (open access)

Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: July 1 - September 30, 1963

Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
Date: November 15, 1963
Creator: Aerojet-General Corporation
System: The UNT Digital Library
Irradiation Behavior of High Purity Uranium (open access)

Irradiation Behavior of High Purity Uranium

Report that "describes the behavior of small, high purity uranium specimens irradiated under controlled conditions" (p. 2).
Date: November 1963
Creator: Leggett, R. D.; Mastel, B. & Bierlein, T. K.
System: The UNT Digital Library
Development and Demonstration of an Ion-Exchange Process for Kilogram-Scale Production of High Purity Promethium (open access)

Development and Demonstration of an Ion-Exchange Process for Kilogram-Scale Production of High Purity Promethium

Report regarding "the development of a process suitable for large-scale separation of highly purified promethium from the trivalent fission product rare earth mixture" (p. 3).
Date: October 1963
Creator: Wheelwright, E. J. (Earl J.) & Roberts, F. P.
System: The UNT Digital Library
A Method for Beta-Gamma Hand and Shoe Counting Under Varying Background Conditions (open access)

A Method for Beta-Gamma Hand and Shoe Counting Under Varying Background Conditions

Report containing a method for beta-gamma counting of hands, shoes, and clothing via an instrument that employs scintillation detectors and solid-state circuits.
Date: October 1963
Creator: Spear, W. G.
System: The UNT Digital Library
Specifications for Swage Compacted, Mixed Oxide (UO2-PuO2), Fuel Elements for the Plutonium Recycle Test Reactor (MARK I-M) (open access)

Specifications for Swage Compacted, Mixed Oxide (UO2-PuO2), Fuel Elements for the Plutonium Recycle Test Reactor (MARK I-M)

Report containing the dimensions, materials, and fabrication details for swage compacted, mixed oxide (UO2-PuO2), fuel elements for the Plutonium Recycle Test Reactor (MARK I-M).
Date: October 1963
Creator: Hanford Atomic Products Operation
System: The UNT Digital Library
Specifications for Vibrationally Compacted, Mixed Oxide (UO2-PuO2), Fuel Elements for the Plutonium Recycle Test Reactor (MARK I-L) (open access)

Specifications for Vibrationally Compacted, Mixed Oxide (UO2-PuO2), Fuel Elements for the Plutonium Recycle Test Reactor (MARK I-L)

Report describing the dimensions, materials, and fabrication of vibrationally compacted, mixed oxide (UO2-PuO2) fuel elements for the Plutonium Recycle Test Reactor (MARK I-L). Appendix begins on page 38.
Date: October 1, 1963
Creator: Hanford Atomic Products Operation
System: The UNT Digital Library
Portable Radiation Survey Instrument (open access)

Portable Radiation Survey Instrument

Report describing a portable radiation survey instrument, its design, and usage.
Date: September 1963
Creator: Sheen, E. M. & Spear, W. G.
System: The UNT Digital Library
In-Pile Loop Corrosion Experiments with Uranyl Sulfate Solutions at 235 and 250 C (open access)

In-Pile Loop Corrosion Experiments with Uranyl Sulfate Solutions at 235 and 250 C

Report presenting in-pile loop experiments DD, EE, FF, GG, L-412, L-413, and L-418, which were seven of a series designed to test the radiation corrosion of zirconium, titanium, and stainless steel alloys in solutions under various conditions of radiation intensity, temperature, solution composition, and velocity of flow. Steel specimens exposed in the loop cores showed increases in corrosive attack over that expected out-of-radiation.
Date: August 15, 1963
Creator: Jenks, G. H. & Baker, J. E.
System: The UNT Digital Library
Protective Clothing Monitoring System (open access)

Protective Clothing Monitoring System

Report describing the development and installation of an automated conveyor-type laundry system for the purpose of monitoring laboratory clothing for beta-gamma contamination.
Date: August 1, 1963
Creator: Rankin, M. O. & Spear, W. G.
System: The UNT Digital Library
The Strain Aging and Heat Treatment Properties of N-Reactor Connector Tubes (open access)

The Strain Aging and Heat Treatment Properties of N-Reactor Connector Tubes

Report regarding the determination of "the susceptibility to strain aging and the effect of stress-relief annealing on the properties of N-reactor connecting tubes made from ASTM A-106 Grade B high carbon steel" (p. 2).
Date: July 30, 1963
Creator: Pessl, H. J.
System: The UNT Digital Library
An Alpha Scintillation Tester for Uranium Surface Contamination of N-Reactor Fuel (open access)

An Alpha Scintillation Tester for Uranium Surface Contamination of N-Reactor Fuel

Report that "describes a nondestructive tester and some of its applications in measuring 10 to 100 µg of uranium surface contamination on unirradiated, low enrichment, uranium fuel elements" (p. ii).
Date: July 1963
Creator: Jackson, C. N., Jr.
System: The UNT Digital Library
In-Pile Radiation Corrosion Experiments with Zirconium, Titanium, and Steel Alloys in 0.17 m UO2SO4 Solutions at 280°C (open access)

In-Pile Radiation Corrosion Experiments with Zirconium, Titanium, and Steel Alloys in 0.17 m UO2SO4 Solutions at 280°C

In-pile loop experiments L-2-15 and L-4-16 were two of a series designed to test the radiation corrosion of Zircaloy-2 and other possible reactor construction materials in UO2SO4 solutions under various conditions of radiation intensities, temperatures, solution compositions, and velocity flow past specimens.
Date: June 10, 1963
Creator: Jenks, G. H.
System: The UNT Digital Library
Health Physics Instrument Manual (open access)

Health Physics Instrument Manual

Report issued by the Oak Ridge National Laboratory discussing a Health Physics Instrument Manual. Descriptions, characteristics, and applications of different instruments are presented. This report includes tables, illustrations, and photographs.
Date: May 16, 1963
Creator: Davis, D. M. & Gupton, E. D.
System: The UNT Digital Library
Corrosion Studies in Simulated N-Reactor Secondary System Water Environment (open access)

Corrosion Studies in Simulated N-Reactor Secondary System Water Environment

Report containing the procedures and results of tests made to determine the corrosion resistance of materials in a simulation of Hanford Laboratories' N-Reactor secondary system water environment.
Date: May 1963
Creator: Larrick, A. P.
System: The UNT Digital Library
Gas-Metal Reactions with Iron- and Nickel-Base Heat Resistant Alloys: An Interpretive Literature Survey (open access)

Gas-Metal Reactions with Iron- and Nickel-Base Heat Resistant Alloys: An Interpretive Literature Survey

Report reviewing literature that concerns "the compatibility of stainless steels and nickel-base alloys with various gases which might be present in or around a high temperature nuclear reactor" (p. 2).
Date: May 1963
Creator: Jones, D. A.
System: The UNT Digital Library
Plutonium Recycle Test Reactor Final Safeguard Analysis: Supplement 5, Fuel Element Rupture Testing Facility Analysis (open access)

Plutonium Recycle Test Reactor Final Safeguard Analysis: Supplement 5, Fuel Element Rupture Testing Facility Analysis

This report describes the final design of the Fuel Element Rupture Testing Facility and summarizes the safeguards analyses of the design and plans for operation.
Date: May 1963
Creator: Hanthorn, H. E.
System: The UNT Digital Library
UT-4: An Automatic Ultrasonic Tester for Closures of Hanford I&E Fuels (open access)

UT-4: An Automatic Ultrasonic Tester for Closures of Hanford I&E Fuels

Report that "describes the equipment, technologies of use, and reliability of an ultrasonic tester - designated UT-4 - capable of detecting very small defects in the brazed closures of reactor fuel elements" (p. 2).
Date: May 1963
Creator: Hunter, D. O. & Zeutschel, M. F.
System: The UNT Digital Library
An Automatic Monitor for As76 Concentrations in Reactor Cooling Water (open access)

An Automatic Monitor for As76 Concentrations in Reactor Cooling Water

Report that describes the development, design, and operation of a prototype instrument meant to monitor the As76 concentration in reactor cooling water streams.
Date: April 1963
Creator: Rieck, H. G. 1922-
System: The UNT Digital Library
High Temperature Short-Time, Uranium Carbide-Metal Reactions (open access)

High Temperature Short-Time, Uranium Carbide-Metal Reactions

Report investigating the compatibility of uranium carbide with tungsten, tantalum, molybdenum, Zircaloy-2, AISI 304L SS, Inconel, Hastelloy F, niobium-1% Zr, and niobium-33% Ta-1% Zr. These pairs were heated together at 1000 C and above for ten minutes.
Date: March 1963
Creator: Christensen, J. A.
System: The UNT Digital Library
Plutonium Recycle Test Reactor Mechanical Seal Pump Operating Experience: August 1960 Through November 1962 (open access)

Plutonium Recycle Test Reactor Mechanical Seal Pump Operating Experience: August 1960 Through November 1962

Report documenting experience gained by operating the spare PRTR Primary Process Pump. This includes descriptions of equipment used, testing procedures, and operating history.
Date: March 1963
Creator: Scott, P. A.
System: The UNT Digital Library
Specifications for Vibrationally Compacted UO2 Nested Tubular Fuel Element (PRTR MARK II-C) (open access)

Specifications for Vibrationally Compacted UO2 Nested Tubular Fuel Element (PRTR MARK II-C)

Report describing the vibrationally compacted UO2 nested tubular fuel element, its design specifications, fabrication, and assembly.
Date: March 1963
Creator: Milhollen, M. K.
System: The UNT Digital Library