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Engineering and Economic Feasibility Study for a Combination Nuclear Power and Desalting Plant: Summary (open access)

Engineering and Economic Feasibility Study for a Combination Nuclear Power and Desalting Plant: Summary

From introduction: This report is an engineering and economic feasibility study of a combination power and desalting plant in Southern California.
Date: January 1966
Creator: Bechtel Corporation
Object Type: Report
System: The UNT Digital Library
Engineering Development of a Foam Column for Countercurrent Surface-Liquid Extraction of Surface-Active Solutes (open access)

Engineering Development of a Foam Column for Countercurrent Surface-Liquid Extraction of Surface-Active Solutes

Report documenting the problems, design, and operation of countercurrent liquid-foam columns.
Date: June 1965
Creator: Haas, P. A.
Object Type: Report
System: The UNT Digital Library
Engineering Evaluation Studies: Heavy Water Moderated Power Reactor Plants (open access)

Engineering Evaluation Studies: Heavy Water Moderated Power Reactor Plants

Foreword: This report describes results of a series of evaluation and design studies conducted between July 1, 1960 and June 30, 1961, related to heavy water moderated power reactor plants.
Date: June 30, 1961
Creator: Chittenden, W. A. & Hoveke, G. F.
Object Type: Report
System: The UNT Digital Library
Engineering Evaluation Studies: Heavy Water Moderated Power Reactor Plants (open access)

Engineering Evaluation Studies: Heavy Water Moderated Power Reactor Plants

Foreword: This report describes the results of a series of engineering evaluation studies conducted between July 1, 1961 and June 30, 1962, related to heavy water moderated power reactor plants.
Date: June 30, 1962
Creator: Chittenden, W. A. & Hoveke, G. F.
Object Type: Report
System: The UNT Digital Library
An Engineering Test Program to Investigate a Loss of Coolant Accident (open access)

An Engineering Test Program to Investigate a Loss of Coolant Accident

From preface: "The purpose of this report is to present an engineering test program for investigating a loss of coolant accident for a pressurized water-cooled and moderated reactor system."
Date: October 1964
Creator: Wilson, T. R.; Hauge, O. M.; Matheney, G. B. & Homer, G. B.
Object Type: Report
System: The UNT Digital Library
Engineering Test Reactor Critical Facility Control System Manual (open access)

Engineering Test Reactor Critical Facility Control System Manual

This report consists of the description, drawings, connections, and schematics of the various control elements that make up the control system of the Engineering Test Reactor Critical Facility (ETRC).
Date: June 23, 1961
Creator: Meichle, F. A.
Object Type: Report
System: The UNT Digital Library
Environmental Analysis of NS "Savannah" Operation at Camden (open access)

Environmental Analysis of NS "Savannah" Operation at Camden

Report regarding the nuclear ship "Savannah" and the consequences of nuclear activity that it would release into the surrounding area at its proposed startup site, Camden, New Jersey. Scenarios include activity being released into the atmosphere and hydrosphere, damage to equipment, and effects on a population.
Date: 1960
Creator: Cottrell, William B.; Mann, L. A.; Parker, F. L. & Schmidt, G. D.
Object Type: Report
System: The UNT Digital Library
EOCR Control Rod and Driver Fuel Hydraulic Tests (open access)

EOCR Control Rod and Driver Fuel Hydraulic Tests

Report discussing the results of experiments on an EOCR prototype control rod, control rod drive, and driver fuel assembly that were extensively tested in 500 deg F Santowax and 132 deg F water. These tests not only established the operating characteristics of these assemblies but also revealed a number of deficiencies in the various components. It includes descriptions of the control rod, control rod drive, and driver fuel assembly together with descriptions of their method of operation.
Date: October 19, 1962
Creator: Harrison, L. J.
Object Type: Report
System: The UNT Digital Library
ETR Nuclear Instrumentation : Final Report (open access)

ETR Nuclear Instrumentation : Final Report

Report regarding the primary nuclear instrumentation at the Engineering Test Reactor (ETR) and early difficulties.
Date: February 3, 1960
Creator: Hanson, D. C.
Object Type: Report
System: The UNT Digital Library
Evaluated Neutron Cross Sections for Tritium (open access)

Evaluated Neutron Cross Sections for Tritium

From foreword: Evaluation of the experimental data on the light isotopes, hydrogen through beryllium, was initiated by LASL in mid-1963. Since the data compilations available were completely inadequate for the task at hand, the tedious program of compiling and plotting was undertaken. As the work progressed an attempt was made to eliminate many of the obvious errors and inconsistencies found in the literature and existing compilations.
Date: February 1965
Creator: Stewart, Leona
Object Type: Report
System: The UNT Digital Library
Evaluation and Design Heavy Water Moderated Power Reactor Plants (open access)

Evaluation and Design Heavy Water Moderated Power Reactor Plants

From foreword: This report investigates the economics and performance of alternate cycles for heavy water moderated power reactors.
Date: June 30, 1960
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Evaluation and Design Heavy Water Moderated Power Reactor Plants (open access)

Evaluation and Design Heavy Water Moderated Power Reactor Plants

From introduction: This report has been prepared to present the details of the heavy water cooled power reactors, including cost estimates, plant design studies, and other work directly related to the current status of D2O reactors.
Date: April 28, 1960
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Evaluation of a Reduced Pressure Backflow Preventer Using Activation Analysis (open access)

Evaluation of a Reduced Pressure Backflow Preventer Using Activation Analysis

Report containing tests performed to evaluate a reduced pressure backflow preventer. This includes preliminary tests, resulting improvements, and final rests. Appendices begin on page 23.
Date: January 1963
Creator: Baird, Justus N., Jr.; Sanford, W. R. & Cristy, G. A.
Object Type: Report
System: The UNT Digital Library
Evaluation of an Engineering Demonstration of the Modified Zirflex and Neuflex Processes for the Preparation of Solvent Extraction Feeds from Unirradiated Zirconium-Base Reactor Fuels (open access)

Evaluation of an Engineering Demonstration of the Modified Zirflex and Neuflex Processes for the Preparation of Solvent Extraction Feeds from Unirradiated Zirconium-Base Reactor Fuels

Report that investigates the concept of using ammonium fluoride-oxidant systems to dissolve spent U-Zr-Sn reactor fuels in both batch and continuous operation.
Date: March 1964
Creator: Kitts, F. G.
Object Type: Report
System: The UNT Digital Library
Evaluation of Diethers as Uranium Extractants (open access)

Evaluation of Diethers as Uranium Extractants

Report on the determination of several physical properties, pertinent to uranium extraction, for a number of ethers and related compounds.
Date: January 14, 1963
Creator: Googin, J. M.; Harper, W. L.; Phillips, L. R. & Postma, Fred W.
Object Type: Report
System: The UNT Digital Library
An Evaluation of Four Processes for Recovering Uranium from Zirconium Fuels at the Idaho Chemical Processing Plant (open access)

An Evaluation of Four Processes for Recovering Uranium from Zirconium Fuels at the Idaho Chemical Processing Plant

Report evaluating the technical and economic feasibility of four zirconium fuel processes: the present STR process, the modified Zirflex process, the barium fluozirconate process, and the sodium formate process.
Date: April 27, 1962
Creator: Burn, P.
Object Type: Report
System: The UNT Digital Library
Evaluation of Iron- and Nickel-Base Alloys for Medium and High Temperature Reactor Applications, Part 1 (open access)

Evaluation of Iron- and Nickel-Base Alloys for Medium and High Temperature Reactor Applications, Part 1

Report discussing the evaluation of the "behavior of austenitic and ferritic stainless steels, iron-chromium-aluminum base alloys and nickel-base superalloys, in medium and high temperature simulated reactor environments" (p. 2).
Date: February 1961
Creator: Pessl, H. J.
Object Type: Report
System: The UNT Digital Library
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.
Object Type: Report
System: The UNT Digital Library
Evaluation of Radiation Stabilizers for Terphenyl by High-Temperature Electron Irradiation (open access)

Evaluation of Radiation Stabilizers for Terphenyl by High-Temperature Electron Irradiation

From summary: "Experiments to determine effectiveness of additives to reduce radiolytic damage to a mixture of isometric terphenyls in which 93 separate compounds were evaluated."
Date: January 23, 1963
Creator: Hartzfeld, H. A. & Regier, R. B.
Object Type: Report
System: The UNT Digital Library
An Evaluation of Reactor Concepts for Use As Separate Steam Superheaters (open access)

An Evaluation of Reactor Concepts for Use As Separate Steam Superheaters

Report estimating the merits of a variety of nuclear reactor concepts for use as external superheaters to be added on to a steam-producing nuclear power plant.
Date: October 1961
Creator: Lennox, D. H.; MacFarlane, D. R.; Brubaker, R. C.; Martinec, E. L.; Rohde, R. R.; Toppel, B. J. et al.
Object Type: Report
System: The UNT Digital Library
Evaluation of Ultimate Disposal Methods for Liquid and Solid Radioactive Wastes: Part 2, Conversion to Solid by Pot Calcination (open access)

Evaluation of Ultimate Disposal Methods for Liquid and Solid Radioactive Wastes: Part 2, Conversion to Solid by Pot Calcination

Economic and hazards calculation of pot calcination of Purex and Thorex wastes.
Date: October 16, 1961
Creator: Perona, J. J.; Bradshaw, R. L.; Roberts, J. T. & Blomeke, J. O.
Object Type: Report
System: The UNT Digital Library
Evaporation of Iron-, Nickel-, and Cobalt-Base Alloys at 760 to 980°C in High Vacuums (open access)

Evaporation of Iron-, Nickel-, and Cobalt-Base Alloys at 760 to 980°C in High Vacuums

Report issued by the Oak Ridge National Laboratory discussing the evaporation of alloys in high vacuums. As stated in the introduction, "the investigation encompasses measurements of the evaporation rates, identification of the evaporating elements, and correlation of these measurements to the alloy composition for specimens in both the polished and oxidized conditions" (p. 2). This report includes tables, illustrations, and photographs.
Date: November 1964
Creator: Bourgette, D. T.
Object Type: Report
System: The UNT Digital Library
Experimental Breeder Reactor-II (EBR-II) Shield Design (open access)

Experimental Breeder Reactor-II (EBR-II) Shield Design

Report describing the EBR-II shield and the methods employed in arriving at the final design. The major shield design problems for that reactor are enumerated and discussed.
Date: September 1962
Creator: Grotenhuis, M.; McArthy, A. E. & Rossin, A. D.
Object Type: Report
System: The UNT Digital Library
An Experimental Investigation of Instantaneous-Collapse and Creep-Buckling Characteristics of Cylindrical Shells (open access)

An Experimental Investigation of Instantaneous-Collapse and Creep-Buckling Characteristics of Cylindrical Shells

Report tests "conducted on nominal 8.0-in.-OD by 0.25-in.-wall and 4.0-in.-OD by 0.12-in.-wall specimens made from commercial pipe and tubing" (p. 1).
Date: 1964
Creator: Greenstreet, B. L. & Corum, J. M.
Object Type: Report
System: The UNT Digital Library