Serial/Series Title

Proceedings of the Symposium on the Solidification and Long-Term Storage of Highly Radioactive Wastes: February 14-18, 1966, Richland, Washington (open access)

Proceedings of the Symposium on the Solidification and Long-Term Storage of Highly Radioactive Wastes: February 14-18, 1966, Richland, Washington

Symposium proceedings regarding long-term storage of highly radioactive wastes resulting from nuclear reactors.
Date: November 1966
Creator: Regan, W. H.
System: The UNT Digital Library
1000-MWe LMFBR Follow-On Study, Task I Report: Volume 1 (open access)

1000-MWe LMFBR Follow-On Study, Task I Report: Volume 1

From introduction: "The objective of this study is to provide information that will assist the Atomic Energy Commission in furthering the National Liquid Metal Fast Breeder Reactor (LMFBR) Program. We plan to accomplish this end, in part, by extending the original studies to include system and component design and parametric evaluations of the nuclear steam supply system and its related systems and subsystems based on an estimation of the state of technology in 1980."
Date: June 1967
Creator: Goulding, B. J.
System: The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1962 (open access)

Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1962

Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile, low-power, nuclear power plant for Military field operation.
Date: August 17, 1962
Creator: Aerojet-General Corporation
System: The UNT Digital Library
In-Pile Loop Investigations of Corrosion of Zircaloy-2 and Other Possible Reactor Materials in 0.04 m UO2SO4 AT 280°C (open access)

In-Pile Loop Investigations of Corrosion of Zircaloy-2 and Other Possible Reactor Materials in 0.04 m UO2SO4 AT 280°C

One of a series of experiments to test the radiation corrosion of Zircaloy-2 and other possible reactor construction materials in UO2SO4 solutions under various radiation intensities, temperatures, solution compositions, and velocities of flow past specimens.
Date: May 5, 1962
Creator: Jenks, G. H.
System: The UNT Digital Library
Measurement of α, the Ratio of the Neutron Capture Cross Section to the Fission Cross Section, for ²³⁵U in the Energy Region from 3.25 eV to 1.8 keV (open access)

Measurement of α, the Ratio of the Neutron Capture Cross Section to the Fission Cross Section, for ²³⁵U in the Energy Region from 3.25 eV to 1.8 keV

Report issued by the Oak Ridge National Laboratory discussing techniques to obtain measurements of alpha for enriched uranium. Descriptions of equipment and experiments used to obtain alpha are presented. This report includes tables, and illustrations.
Date: April 1965
Creator: deSaussure, G.; Weston, L. W.; Gwin, R.; Russell, J. E. & Hockenbury, R. W.
System: The UNT Digital Library
Nuclear Safety Program Semiannual Progress Report: for Period Ending June 30, 1962 (open access)

Nuclear Safety Program Semiannual Progress Report: for Period Ending June 30, 1962

Report that describes the research and developments of the Nuclear Safety Research and Development Program of the Oak Ridge National Laboratory.
Date: August 24, 1962
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
Nuclear Power and Water Desalting Plants for Southwest United States and Northwest Mexico: A Preliminary Assessment (open access)

Nuclear Power and Water Desalting Plants for Southwest United States and Northwest Mexico: A Preliminary Assessment

From introduction: Preliminary assessment between the United States, Mexico, and the IAEA on the technical and economic practicability of a dual-purpose nuclear power plant designed to produce fresh water and electricity for the southern border portion of the Colorado River.
Date: September 1968
Creator: unknown
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.
System: The UNT Digital Library
Fuels and Materials Development Program Quarterly Progress Report, September 30, 1968 (open access)

Fuels and Materials Development Program Quarterly Progress Report, September 30, 1968

From Foreword: "Report containing information about ongoing research and development taking place in the Oak Ridge National Laboratory's Fuels and Materials Development Program. This includes a series of test reports covering such subjects as reactor fuels, the development of nitride fuels, and the effects of radiation on structural materials."
Date: February 1969
Creator: Oak Ridge National Laboratory. Metals and Ceramics Division.
System: The UNT Digital Library
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
Hydrogen and Other Synthetic Fuels: A Summary of the Work of the Synthetic Fuels Panel (open access)

Hydrogen and Other Synthetic Fuels: A Summary of the Work of the Synthetic Fuels Panel

From introduction: This report covers all aspects of an energy system based on nonfossil synthetic fuels and includes discussions on the production of the fuels; their storage, transmission, and end uses; and an overall systems analysis illustrating the role these fuels might assume in the future.
Date: September 1972
Creator: unknown
System: The UNT Digital Library
Molten-Salt Reactor Program Semiannual Progress Report, February 28, 1962 (open access)

Molten-Salt Reactor Program Semiannual Progress Report, February 28, 1962

Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Molten-Salt Reactor Program. Descriptions of design, construction, and experimental progress are presented. This report includes tables, illustrations, and photographs.
Date: 1962
Creator: Oak Ridge National Laboratory
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
System: The UNT Digital Library
Puerto Rico Energy Center Study: Volume 2 (open access)

Puerto Rico Energy Center Study: Volume 2

From introduction: This report concerns nuclear power plant deployment in Puerto Rico.
Date: July 1970
Creator: Burns and Roe
System: The UNT Digital Library
Chemical Technology Division Annual Progress Report: for Period Ending May 31, 1969 (open access)

Chemical Technology Division Annual Progress Report: for Period Ending May 31, 1969

Report documenting the ongoing research and development of the Oak Ridge National Laboratory's Chemical Technology Division.
Date: October 1969
Creator: Oak Ridge National Laboratory. Chemical Technology Division.
System: The UNT Digital Library
Health and Safety Laboratory Fallout Program Quarterly Summary Report: September 1, 1960 - December 1, 1960 (open access)

Health and Safety Laboratory Fallout Program Quarterly Summary Report: September 1, 1960 - December 1, 1960

Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date: January 9, 1961
Creator: Hardy, Edward P., Jr.; Rivera, Joseph & Frankel, Robert
System: The UNT Digital Library
Homogeneous Reactor Project Quarterly Progress Report: November 1959-January 1960 (open access)

Homogeneous Reactor Project Quarterly Progress Report: November 1959-January 1960

From Summary: "The major objective of the run was the investigation of fuel stability. The reactor operated for long periods at the design power of 5 Mw with none of the usual indications of instability while the system pressure was kept at 1250 psig. Run 21 ended on January 22, so that the reason for an abrupt change in the mixing rate of fuel between the core and blanket could be investigated and a reactor steam-system valve could be repaired."
Date: April 29, 1960
Creator: Briggs, R. B.
System: The UNT Digital Library
Liquid Metal Fuel Reactor Experiment Quarterly Technical Report: July - September 1958 (open access)

Liquid Metal Fuel Reactor Experiment Quarterly Technical Report: July - September 1958

Report containing research and development undertaken regarding the Liquid Metal Fuel Reactor Experiment.
Date: October 1958
Creator: Babcock & Wilcox Company
System: The UNT Digital Library
Atomic Energy Facts: a Summary of Atomic Activities of Interest to Industry (open access)

Atomic Energy Facts: a Summary of Atomic Activities of Interest to Industry

Introduction: Atomic Energy Facts is designed to serve as an introduction to nuclear operations in the United States and as a handbook of related information for the use of industrial firms and other active or interested in atomic energy.
Date: September 1957
Creator: U.S. Atomic Energy Commission
System: The UNT Digital Library
A Computer Program for Determining First-Collision Neutron Doses (open access)

A Computer Program for Determining First-Collision Neutron Doses

Data processing program written to compute the neutron dose received by individuals exposed in a nuclear excursion.
Date: May 21, 1962
Creator: McMurray, C. S.
System: The UNT Digital Library
Gas-Cooled Reactor Project Semiannual Progress Report: September 1964 (open access)

Gas-Cooled Reactor Project Semiannual Progress Report: September 1964

Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Gas-Cooled Reactor Program. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.
Date: February 1965
Creator: Trauger, D. B. & Whitman, G. D.
System: The UNT Digital Library
Chemical Technology Division Annual Progress Report: for Period Ending May 31, 1963 (open access)

Chemical Technology Division Annual Progress Report: for Period Ending May 31, 1963

Report issued by Oak Ridge National Laboratory that describes research and progress at the Chemical Technology Division.
Date: September 20, 1963
Creator: Oak Ridge National Laboratory. Chemical Technology Division.
System: The UNT Digital Library
Homogeneous Reactor Project Quarterly Progress Report: August-October 1957 (open access)

Homogeneous Reactor Project Quarterly Progress Report: August-October 1957

Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Homogeneous Reactor Project. Progress of operations, design, development, and analysis is presented. This report includes tables, illustrations, and photographs.
Date: January 21, 1958
Creator: Briggs, R. B.; Winters, C. E.; Beall, S. E.; Lane, J. A.; Bohlmann, E. G.; Ferguson, D. E. et al.
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