Resource Type

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
Transistorized Pulse Counting Equipment (open access)

Transistorized Pulse Counting Equipment

This instrument was designed primarily to meet the need for radiation monitoring equipment in chemical process areas where corrosive vapors exist.
Date: July 26, 1960
Creator: Henry, John J.
System: The UNT Digital Library
Transportation Energy Flows for 1976 (open access)

Transportation Energy Flows for 1976

Diagrams provided for a convenient overview and standardized framework of the United States transportation system.
Date: December 1980
Creator: Kidman, R. B.
System: The UNT Digital Library
Tube-To-Tubesheet Welding Development Programs to 30 Megawatt Prototype Sodium Intermediate heat Exchanger and Steam Generator (open access)

Tube-To-Tubesheet Welding Development Programs to 30 Megawatt Prototype Sodium Intermediate heat Exchanger and Steam Generator

Special welding techniques for joining Inconel weld overlays on type 316 stainless steel tubesheets and channels are described. The program for the development of the required welding procedures are divided into three specific programs: overlaying Inconel filler Metal 82 on type 316 stainless steel, welding type 316 stainless steel tubes to a type 316 stainless steel tubesheet, and welding Inconel-type 316 stainless steel composite tubes to Inconel weld overlaid type 316 tubesheets. Shock tests are described which attempt to assimilate the most drastic thermal transient that could occur in both units and to evaluate the effect of the resulting stresses on the Inconel overlay and the tube-to-tubesheet welds. (N.W.R.)
Date: 1963
Creator: Alco Products (Firm).
System: The UNT Digital Library
U.S. Reactor Containment Technology: a Compilation of Current Practice in Analysis, Design, Construction, Test, and Operation, Volume 1 (open access)

U.S. Reactor Containment Technology: a Compilation of Current Practice in Analysis, Design, Construction, Test, and Operation, Volume 1

First volume of a compilation of information about reactor containment, written by experts from a variety of organizations.
Date: August 1965
Creator: Cottrell, William B. & Savolainen, A. W.
System: The UNT Digital Library
U.S. Reactor Containment Technology: a Compilation of Current Practice in Analysis, Design, Construction, Test, and Operation, Volume 2 (open access)

U.S. Reactor Containment Technology: a Compilation of Current Practice in Analysis, Design, Construction, Test, and Operation, Volume 2

Second volume of a compilation of information about reactor containment, written by experts from a variety of organizations.
Date: 1965
Creator: Cottrell, William B. & Savolainen, A. W.
System: The UNT Digital Library
Ultrasonic Resin Level Detector (open access)

Ultrasonic Resin Level Detector

This report describes the development of an ultrasonic instrument for resin level measurements in an ion exchange column.
Date: January 15, 1960
Creator: Hunter, D. O. & Pleasance, C. L.
System: The UNT Digital Library
Uranium Concentration Meter (open access)

Uranium Concentration Meter

From abstract; "Two basic instruments were developed for determining the concentration of uranium in solutions. Both instruments detect the gamma activity present in a sample solution, and interpret this analysis into direct presentation as parts per million."
Date: September 24, 1956
Creator: Arnett, Orville
System: The UNT Digital Library
Uranium Production - Process Designs for Leached Zone Plants Volume 3. Alumina Recovery Section (open access)

Uranium Production - Process Designs for Leached Zone Plants Volume 3. Alumina Recovery Section

Processing of Florida leached zone material for the recovery of alumina.
Date: April 13, 1955
Creator: Clements, D. F.; Williams, W. B.; McCullough, R. F. & Wrege, E. E.
System: The UNT Digital Library
VBWR Stability Test Report (open access)

VBWR Stability Test Report

Analysis of the stability of boiling water reactors.
Date: June 1963
Creator: U.S. Atomic Energy Commission
System: The UNT Digital Library
A Versatile Spectrometer Magnet Power Supply (open access)

A Versatile Spectrometer Magnet Power Supply

Early results from actual laboratory operation of a more versatile magnet supply.
Date: April 15, 1963
Creator: Groppe, W. A.
System: The UNT Digital Library
Welded Repair of Fill and Drain Holes in High-Carbon Steel Gas Storage Cylinders (open access)

Welded Repair of Fill and Drain Holes in High-Carbon Steel Gas Storage Cylinders

Report discussing the results of fill and drain holes for hydrostatic pressure tests on head knuckle radius of forged-steel gas storage cylinders.
Date: November 5, 1964
Creator: Thompson, J. C. & Lambert, F. J.
System: The UNT Digital Library
X-Ray Fluorescence Tables: Program Description (open access)

X-Ray Fluorescence Tables: Program Description

Report discussing the mechanics of X-Ray and COMBO computer programs.
Date: July 20, 1964
Creator: Amsbury, W. P.; Lee, W. W.; Rowan, J. H. & Walden, G. E.
System: The UNT Digital Library
Zero Power Experiments for the SM-1 Core II : Task XV (open access)

Zero Power Experiments for the SM-1 Core II : Task XV

Abstract: An element by element reactivity check for SM-1 Core II fuel elements and control rod absorber sections was performed and the burnable nuclear poison loading in the SM-1 Core II stationary fuel elements was established. An approach to criticality of the SM-1 Core II was performed by the inverse multiplication method and the critical rod bank position obtained as a function of fuel loading up to the full SM-1 Core II loading. Maximum and minimum core reactivity measurements were obtained by selective loading of stationary fuel elements and the total "excess K" for the core established. Power distribution measurements in the region of the core-reflector interface and the fuel-absorber interface in the control rod assemblies were performed. The effectiveness of europium flux suppressors in the top of control rod fuel elements and the power peaking in stationary elements adjacent to water gaps in control rod assemblies were measured. Survey measurements established the worth of spiking cold clean SM-1 cores with SM-2 elements, and of water holes in the SM-1 core which might be utilized as flux traps for materials irradiation.
Date: March 15, 1960
Creator: Robinson, R. A.; Weiss, S. H.; McCool, W. J. & Schrader, E. W.
System: The UNT Digital Library
Zirconium-Hafnium Separation : Mixer-Settler Studies : Final Report (open access)

Zirconium-Hafnium Separation : Mixer-Settler Studies : Final Report

Abstract: Use of the mixer-settler apparatus as a rapid means of determining improved conditions for plant operation is described including the experimental details. The preparation of highly purified samples of both zirconium oxide and hafnium oxide is discussed. (This document is concerned almost entirely with explorations of small scale continuous systems. Another document dealing with this general problem using small scale batch operations is being published simultaneously. It should prove of advantage to the reader to study this companion report, Document Y-611, by Barton, Overholser, and Grimes, to obtain a complete picture of the available information.).
Date: November 17, 1955
Creator: Waldrop, F. B.; Ward, W. T. & Leaders, W. M.
System: The UNT Digital Library