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A Transistorized GM Survey Instrument (open access)

A Transistorized GM Survey Instrument

A portable GM survey instrument was designed and developed which consists of a single transistor blocking-oscillator high voltage supply, a dual transistor multivibrator count-rate meter and a standard 30 mg/cm² glass-wall GM tube.
Date: January 5, 1956
Creator: Spear, W. G.
Object Type: Report
System: The UNT Digital Library
The 4K ANGIE Code (open access)

The 4K ANGIE Code

The ANGIE, one of a series of reactor neutronic programs for an IBM 709 or 7090 data processing system, solves the time-dependent, multi-group, neutron diffusion equation for 1 to 26 energy groups applied to a rectangular mesh superimposed on either an x-y or an r-z plane.
Date: March 5, 1962
Creator: Stone, Stuart P.
Object Type: Report
System: The UNT Digital Library
Strontium Sorption Studies Using Naturally Occurring Ion Exchange Materials (open access)

Strontium Sorption Studies Using Naturally Occurring Ion Exchange Materials

Four naturally occurring materials, namely, vermiculite, variscite, Tennessee rock phosphate, and Florida pebble phosphate, were studied to determine the feasibility of their use in columns for the sorption of strontium from high pH, intermediate-level wastes produced at ORNL. Excepting vermiculite, all materials were found to be effective in strontium removal.
Date: December 5, 1960
Creator: Thomas, K. T.; Jacobs, D. G.; Tamura, T. & Struxness, E. G.
Object Type: Report
System: The UNT Digital Library
The Uranium-Titanium Alloy System (open access)

The Uranium-Titanium Alloy System

Abstract: "A uranium-titanium constitution diagram is presented. There is complete solid solubility between titanium and gamma uranium above about 2100 F. Only one compound exists in the system. It has a hexagonal structure based on U2Ti. It has a fairly wide range of stability, particularly on the titanium side. Beta-titanium solid solution decomposes eutectoidally into alpha titanium and compound at 1150 F. Eutectoid composition is about 72 atomic per cent titanium. Gamma-uranium solid solution decomposes eutectoidally at 1325 F into beta uranium and compound. Eutectoid composition is about 6 atomic per cent titanium. Beta uranium and compound react peritectoidally at 1233 F to give alpha uranium. Solubility of titanium in alpha and beta uranium is low as is the solubility or uranium in alpha titanium."
Date: November 5, 1952
Creator: Udy, Murray C. & Boulger, Francis W.
Object Type: Report
System: The UNT Digital Library
Welding of High-Strength Stainless Steels for Pressure Vessels (open access)

Welding of High-Strength Stainless Steels for Pressure Vessels

The following report describes the welding characteristics of several high-strength stainless steels that were considered for use as a pressure vessel to operate at high pressures at 800 F.
Date: April 5, 1954
Creator: Vagi, J. J.; Thompson, V. R. & Martin, D. C.
Object Type: Report
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.
Object Type: Report
System: The UNT Digital Library
Research Study on Neutron Interactions in Matter as Related to Image Formation (open access)

Research Study on Neutron Interactions in Matter as Related to Image Formation

Report discussing a study on neutron detection schemes and the effect of neutron scattering on neutron image formation quality.
Date: December 5, 1960
Creator: Watts, H. V. & Stone, C. A.
Object Type: Report
System: The UNT Digital Library
A Study of the Wear and Galling of Autoclaved Zircaloy-2 By Various Materials (open access)

A Study of the Wear and Galling of Autoclaved Zircaloy-2 By Various Materials

This is the third of a series of reports describing the phases of a study of the wear and galling of autoclavedZircaloy-2 by various bearing surface materials. The first report (1) showed that increasing contact area between the autoclaved Zircaloy-2 surfaces will not prevent scratching. It also showed that metals softer than Zircaloy-2 in general do not scratch it. The second report (2) described how eight metals and alloys were wear-tested on autoclaved Zircaloy-2 as prospects for fuel element support-bearing surface materials.
Date: July 5, 1960
Creator: Weber, J. W.
Object Type: Report
System: The UNT Digital Library
EURATOM PROGRAM "Improved Zirconium Alloys" (open access)

EURATOM PROGRAM "Improved Zirconium Alloys"

Introduction: "This report is an expanded version of the regular monthly letter report and is prepared in this form with the intention of reviewing work on the subject program for Euratom technical personnel. Work performed during the month of September, which normally constitutes the entire letter report, has been condensed under one heading."
Date: October 5, 1960
Creator: Weinstein, Daniel & Van Thyne, R. J.
Object Type: Report
System: The UNT Digital Library
Improved Zirconium Alloys : Ninth Monthly Report Covering the Period December 1 to December 31, 1960 (open access)

Improved Zirconium Alloys : Ninth Monthly Report Covering the Period December 1 to December 31, 1960

The following report is the ninth in a series of monthly reports covering the program with the objective of developing alloys having superior 680 F water and/or 750 to 900 F steam corrosion resistance, as well as developing higher strength alloys for current temperature ranges while still maintaining corrosion resistance comparable to that of Zircaloy-2. This report was made covering the period December 1 to December 31, 1960.
Date: January 5, 1961
Creator: Weinstein, Daniel & Van Thyne, R. J.
Object Type: Report
System: The UNT Digital Library
Decontamination of ORNL Purex Pilot Plant (open access)

Decontamination of ORNL Purex Pilot Plant

From abstract: "This report describes the decontamination of Oak Ridge National Laboratory Purex Pilot Plant facilities and presents an appraisal of the decontaminating techniques and reagents which were employed."
Date: May 5, 1952
Creator: Wood, H. P.
Object Type: Report
System: The UNT Digital Library
High Pressure Pump Seal Development (open access)

High Pressure Pump Seal Development

"Test results indicated that graphite is not suitable for seal face material. A program to evaluate various materials and seal face geometries was initiated. A seal run using nucerite-bearium combination was carried on for six hours."
Date: March 5, 1962
Creator: Zanoni, P. J.
Object Type: Report
System: The UNT Digital Library