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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.
Object Type: Report
System: The UNT Digital Library
Recovery of Aluminum Nitrate Nonahydrate from Redox Acid Waste, Part 1: Computer Study (open access)

Recovery of Aluminum Nitrate Nonahydrate from Redox Acid Waste, Part 1: Computer Study

Report describing an analog computer simulation of a counter-current crystallization process for use in the recovery of aluminum nitrate nonahydrate from redox acid waste
Date: July 1964
Creator: Godfrey, W. L. & Benham, R. D.
Object Type: Report
System: The UNT Digital Library
Gas-Cooled Reactor Project Semiannual Progress Report: March 1963 (open access)

Gas-Cooled Reactor Project Semiannual Progress Report: March 1963

Report documenting the design and testing progress of the Oak Ridge National Laboratory's Gas-Cooled Reactor Program.
Date: July 23, 1963
Creator: Oak Ridge National Laboratory
Object Type: Report
System: The UNT Digital Library
In-Pile Loop Tests of GCRE Elements (I-IT and I-I'T) (open access)

In-Pile Loop Tests of GCRE Elements (I-IT and I-I'T)

Report documenting two in-pile loop experiments conducted at the Battelle Research Reactor-Gas Cooled Reactor (BRR-GCR). These experiments test heat transfer calculations and the behavior of the fuel element under severe thermal-cycling conditions.
Date: July 2, 1959
Creator: Nakazato, S.; Williams, P. M. & Wilson, W. D.
Object Type: Report
System: The UNT Digital Library
The Design of a Dynamic Corrosion and Chemical Control Test Loop and Preliminary Out-of-Pile Test Results (open access)

The Design of a Dynamic Corrosion and Chemical Control Test Loop and Preliminary Out-of-Pile Test Results

From abstract: "This report describes the overall loop design and the means by which this design was developed. These include critical facility measurements, analog computer calculations, hydraulic and heat transfer computations, and the construction and operation of an out-of-pile mock-up loop to determine the dynamic characteristics of the loop."
Date: July 12, 1963
Creator: Zelezny, W. F.
Object Type: Report
System: The UNT Digital Library
Fundamentals in the Operation of Nuclear Test Reactors: Volume 3 Engineering Test Design and Operation (open access)

Fundamentals in the Operation of Nuclear Test Reactors: Volume 3 Engineering Test Design and Operation

Engineering test reactor design and operation.
Date: July 1964
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Inline Densimeter for Pulsed Column Liquid Density Pulse Amplitude, and Pulse Frequency Measurements (open access)

Inline Densimeter for Pulsed Column Liquid Density Pulse Amplitude, and Pulse Frequency Measurements

Laboratory fabrication and testing of an inline densimeter.
Date: July 19, 1961
Creator: Mackey, T. S.
Object Type: Report
System: The UNT Digital Library
Siting of Fuel Reprocessing Plants and Waste Management Facilities (open access)

Siting of Fuel Reprocessing Plants and Waste Management Facilities

Report documenting the a study with the goal of identifying the factors that might influence the growth patterns of the fuel processing industry, especially regarding the siting of reprocessing and disposal facilities for high-level waste.
Date: July 1970
Creator: Oak Ridge National Laboratory. Chemical Technology Division.
Object Type: Report
System: The UNT Digital Library
Health and Safety Laboratory Fallout Program Quarterly Summary: March 1, 1974 - June 1, 1974 (open access)

Health and Safety Laboratory Fallout Program Quarterly Summary: March 1, 1974 - June 1, 1974

Report documenting radioactive fallout across the world, including both material in the atmosphere and that has deposited into food supplies.
Date: July 1, 1974
Creator: U.S. Atomic Energy Commission. Health and Safety Laboratory.
Object Type: Report
System: The UNT Digital Library
Health and Safety Laboratory Fallout Program Quarterly Summary Report: March 1, 1974 - June 1, 1974, Appendix (open access)

Health and Safety Laboratory Fallout Program Quarterly Summary Report: March 1, 1974 - June 1, 1974, Appendix

Report documenting radioactive fallout across the world, including both material in the atmosphere and that has deposited into food supplies. This appendix includes tables of monthly fallout deposition collections from 116 sites across the Earth and a list of radionuclides and their half-lives.
Date: July 1, 1974
Creator: U.S. Atomic Energy Commission. Health and Safety Laboratory.
Object Type: Report
System: The UNT Digital Library
Description and Some Safeguard Aspects of Proposed Developmental Fast Neutron Breeder Reactor (open access)

Description and Some Safeguard Aspects of Proposed Developmental Fast Neutron Breeder Reactor

Report that generally describes sodium cooled fast reactors, the features and facilities of such a reactor proposed by Atomic Power Development Associates, and then its safety and siting considerations.
Date: July 25, 1955
Creator: Atomic Power Development Associates
Object Type: Report
System: The UNT Digital Library
Hazards Summary Report for the Army Package Power Reactor (open access)

Hazards Summary Report for the Army Package Power Reactor

APPR-1 is described and the various hazards are reviewed.
Date: July 27, 1955
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Gas Cooled Nuclear Reactor Study (open access)

Gas Cooled Nuclear Reactor Study

Study of a gas cooled reactor with design specifications providing for a source of high temperature heat to a stream of helium. This reactor, in turn, is used as a source of heat for the air stream in a gas-turbine power plant.
Date: July 31, 1956
Creator: Thompson, A. S.
Object Type: Report
System: The UNT Digital Library
Gas-Cooled Reactor Project Semiannual Progress Report: March 1964 (open access)

Gas-Cooled Reactor Project Semiannual Progress Report: March 1964

Report documenting ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Project. From summary: "A study was made of the effect of the energy of extraneous source neutrons on the amplitudes of higher modes in the flux distribution of a subcritical reactor."
Date: July 1964
Creator: Oak Ridge National Laboratory
Object Type: Report
System: The UNT Digital Library
Effect of Process Variables on Graphite Purity (open access)

Effect of Process Variables on Graphite Purity

Results of four experimental heats run at the end of the G-5 contract in the National Carbon Company Clarksburg production furnaces.
Date: July 20, 1954
Creator: Riley, W. C. & Corners, A. M.
Object Type: Report
System: The UNT Digital Library
Joint Design for Making Root Pass Welds without Filler Material (open access)

Joint Design for Making Root Pass Welds without Filler Material

Investigation to evaluate some of the designs, techniques, and methods for fabrication of a root pass.
Date: July 9, 1956
Creator: Lemon, L. C. & Smith, W. R.
Object Type: Report
System: The UNT Digital Library
Fabrication of the PRTR Zircaloy-2 High Pressure Process Tubes (open access)

Fabrication of the PRTR Zircaloy-2 High Pressure Process Tubes

Development of a fabrication process and the manufacture of 95 PRTR process tubes demonstrates that the commercial fabrication of high quality Zircaloy-2 pressure tubing is feasible.
Date: July 31, 1959
Creator: Knecht, R. L.
Object Type: Report
System: The UNT Digital Library
The Possibility of Enhanced Hg202 as a Source of Monochromatic Light (open access)

The Possibility of Enhanced Hg202 as a Source of Monochromatic Light

This report discusses enhanced Hg202 as a source of monochromatic light in relation to the effects of the isotopic impurities.
Date: July 18, 1949
Creator: McNally, J. Rand, Jr.; Griffin, P. M. & Burkhart, L. E.
Object Type: Report
System: The UNT Digital Library
Engineering Test Reactor : Engineering Design and Safeguards Report (open access)

Engineering Test Reactor : Engineering Design and Safeguards Report

From abstract: "Detail and engineering drawings for the Engineering Test Reactor."
Date: July 1956
Creator: Kaiser Engineers
Object Type: Report
System: The UNT Digital Library
A Neutron Absorption Alignment Chart (open access)

A Neutron Absorption Alignment Chart

From introduction: "Neutron absorption alignment chart for the measurement of neutron flux density."
Date: July 30, 1957
Creator: Nisle, Robert G.
Object Type: Report
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.
Object Type: Report
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.
Object Type: Report
System: The UNT Digital Library
An Investigation of a "Dynamic" Theory for Mass Transfer (open access)

An Investigation of a "Dynamic" Theory for Mass Transfer

A new theory is proposed to evaluate individual mass-transfer coefficients without actual experiment.
Date: July 18, 1960
Creator: Schappel, Richard B.
Object Type: Report
System: The UNT Digital Library
Numerical Results for EGCR Moderator-Element Stress Problems (open access)

Numerical Results for EGCR Moderator-Element Stress Problems

From introduction: "A recent report describes the development of a general program for the IBM Type 7090 electronic computer for calculating plane thermal stresses."
Date: July 3, 1961
Creator: Hulbert, Lewis E. & Redmond, Robert F.
Object Type: Report
System: The UNT Digital Library