Resource Type

1,729 Matching Results

Results open in a new window/tab.

Mining and Furnacing Mercury Ore at the New Idria Mine, San Benito County, California (open access)

Mining and Furnacing Mercury Ore at the New Idria Mine, San Benito County, California

Report issued by the U.S. Bureau of Mines discussing mining methods and operations of mercury at the New Idria Mine. As stated in the introduction, "the purpose of this report is to promote the development and conservation of our mineral resources by dissemination of technological information on mining and processing procedures, and related practices at operating mines" (p. 1). This report includes maps, tables, illustrations, and photographs.
Date: 1961
Creator: Linn, R. K. & Dietrick, W. F.
System: The UNT Digital Library
Argonne National Laboratory Idaho Division Summary Report: October 1960-March 1961 (open access)

Argonne National Laboratory Idaho Division Summary Report: October 1960-March 1961

Report issued by the Argonne National Laboratory discussing a summary of projects conducted with the Idaho Division. Descriptions of each project are presented. This report includes tables, and illustrations.
Date: 1961
Creator: Argonne National Laboratory. Idaho Division.
System: The UNT Digital Library
FCC Reports, Volume 30, January 13, 1961 to July 7, 1961 (open access)

FCC Reports, Volume 30, January 13, 1961 to July 7, 1961

Biweekly, comprehensive compilation of decisions, reports, public notices, and other documents of the U.S. Federal Communications Commission. Syllabi index begins on page 1093.
Date: 1961
Creator: United States. Federal Communications Commission.
System: The UNT Digital Library
Interim Report on Corrosion by Zirconium-Base Fluorides (open access)

Interim Report on Corrosion by Zirconium-Base Fluorides

Report issued by the Oak Ridge National Laboratory discussing studies conducted on corrosion by fluorides. Equipment, procedures, results, and analysis is presented. This report includes tables, illustrations, and photographs.
Date: January 17, 1961
Creator: Adamson, G. M.; Crouse, R. S. & Manly, W. D.
System: The UNT Digital Library
A Study of the Feasibility of a Small Scale Reprocessing Plant for the Dresden Nuclear Power Station (open access)

A Study of the Feasibility of a Small Scale Reprocessing Plant for the Dresden Nuclear Power Station

Report describing the design, feasibility, and economic concerns of a small-scale reprocessing plant.
Date: April 28, 1961
Creator: Schneider, H.; Fletcher, R. D.; Codding, J. W.; Bearden, R. G.; Erickson, E. E.; Horn, S. J. et al.
System: The UNT Digital Library
Research and Development Studies on Waste Storage Process (open access)

Research and Development Studies on Waste Storage Process

Report documenting "the determination of the thermal stability of various fission product oxides and nitrates, and an investigation of the gas phase decomposition of ruthenium tetroxide" (p. 4).
Date: May 19, 1961
Creator: Ortner, M. H.; Anderson, C. J. & Campbell, P. F.
System: The UNT Digital Library
The Design, Installation, and Testing of the Gas-Cooled Reactor UOâ‚‚ Irradiation Experiment at the NRTS (open access)

The Design, Installation, and Testing of the Gas-Cooled Reactor UOâ‚‚ Irradiation Experiment at the NRTS

Report regarding sixteen experiments performed with a miniature re-entrant gas loop. Includes design problems and difficulties encountered, as well as their solutions.
Date: September 8, 1961
Creator: Porter, E. H.
System: The UNT Digital Library
Corn Pone: A Multigroup, Multiregion Reactor Code (open access)

Corn Pone: A Multigroup, Multiregion Reactor Code

Report covering the development of a set of difference equations for machine solution. In addition, this report serves as user's manual for Corn Pone, which is a code for the Oracle, the Oak Ridge National Laboratory computer.
Date: 1961?
Creator: Kinney, W. E. & Coveyou, R. R.
System: The UNT Digital Library
Laboratory Development of a Tributyl Phosphate Solvent Extraction Process for Processing 20% Enriched Uranium Alloy Fuel (open access)

Laboratory Development of a Tributyl Phosphate Solvent Extraction Process for Processing 20% Enriched Uranium Alloy Fuel

Report containing a preliminary chemical flowsheet "for the preparation of feed and two solvent extraction cycles for the processing of silicon-containing aluminum-uranium alloy, 20% enriched, fuel elements" (p. 2).
Date: 1961
Creator: Goode, J. H. & Flanary, J. R.
System: The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: July 1 - December 31, 1960 (open access)

Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: July 1 - December 31, 1960

Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
Date: February 22, 1961
Creator: Aerojet-General Corporation
System: The UNT Digital Library
[Arrest Report for George Senator] (open access)

[Arrest Report for George Senator]

Photocopy of an arrest report for George Senator. The report is illegible.
Date: September 12, 1961
Creator: Dallas (Tex.). Police Department.
System: The Portal to Texas History
University of Chicago Laboratory of Molecular Structure and Spectra Technical Report: 1959-1960 (open access)

University of Chicago Laboratory of Molecular Structure and Spectra Technical Report: 1959-1960

Report containing articles, manuscripts, and tabulations of recorded spectra created by the Spectroscopic Laboratory of the University of Chicago.
Date: 1961~
Creator: University of Chicago. Laboratory of Molecular Structure and Spectra.
System: The UNT Digital Library
Gas-Cooled Reactor Project Quarterly Progress Report: December 1960 (open access)

Gas-Cooled Reactor Project Quarterly Progress Report: December 1960

Report documenting the research and development of the Oak Ridge National Laboratory's Gas-Cooled Reactor Project.
Date: 1961
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
Gas-Cooled Reactor Project Quarterly Progress Report: March 1961 (open access)

Gas-Cooled Reactor Project Quarterly Progress Report: March 1961

Report documenting ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Project.
Date: 1961
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
Gas-Cooled Reactor Project Quarterly Progress Report: June 1961 (open access)

Gas-Cooled Reactor Project Quarterly Progress Report: June 1961

Report documenting the ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Program.
Date: 1961
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
Gas-Cooled Reactor Project Quarterly Progress Report: September 1961 (open access)

Gas-Cooled Reactor Project Quarterly Progress Report: September 1961

Report containing the ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Program.
Date: 1961
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
The Thermal Hydraulics Laboratory at Hanford (open access)

The Thermal Hydraulics Laboratory at Hanford

Report describing the experimental facilities of Hanford's Thermal Hydraulics Laboratory, its equipment, personnel, operating schedules, and safety procedures. Appendix begins on page 49.
Date: November 1961
Creator: Batch, J. M.; Toyoda, K. G. & Hanthorn, H. E.
System: The UNT Digital Library
Steam Cooled Power Reactor Evaluation - Beloyarsk (Ural) Reactor (open access)

Steam Cooled Power Reactor Evaluation - Beloyarsk (Ural) Reactor

Report evaluating "the effects of nuclear steam superheating, as utilized in the Russian design, on the economics of electric power production, assuming the use of such a design in the United States" (p. 1). This report includes a description of the Beloyarsk Station and modifications made to the Russian designs for use in the United States.
Date: April 1961
Creator: Hanford Works
System: The UNT Digital Library
The RBU Reactor-Burnup Code: Formulation and Operation Procedures (open access)

The RBU Reactor-Burnup Code: Formulation and Operation Procedures

Report discussing the computer program RBU, which calculates the neutron, reactivity, and isotopic history of a nuclear reactor in such a way as to facilitate the predictions of fuel costs and reactor performance. This report documents RBU's various calculations and operating procedures.
Date: July 1961
Creator: Triplett, J. R.; Merrill, E. T. & Burr, J. R.
System: The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1961 (open access)

Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1961

Report regarding the ongoing research and development related to the Army Gas-Cooled Reactor Systems Program. Includes status and progress of the program's projects, experiments, and data evaluations.
Date: August 10, 1961
Creator: Aerojet-General Corporation
System: The UNT Digital Library
Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 2 - The Mark 1-H (open access)

Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 2 - The Mark 1-H

Report describing the fabrication of of the I-H aluminum-plutonium spike enrichment fuel elements for the Plutonium Recycle Test Reactor (PRTR), including the materials used and design specifications. Appendix begins on page 28.
Date: March 1961
Creator: Sharp, R. E.
System: The UNT Digital Library
Oak Ridge National Laboratory Intrumentation and Controls Division Annual Progress Report: 1960 (open access)

Oak Ridge National Laboratory Intrumentation and Controls Division Annual Progress Report: 1960

Report containing ongoing research and experiments of the Oak Ridge National Laboratory's Instrumentation and Controls Division.
Date: February 3, 1961
Creator: Oak Ridge National Laboratory. Instrumentation and Controls Division.
System: The UNT Digital Library
Superposition of Forced and Diffusive Flow in a Large-Pore Graphite (open access)

Superposition of Forced and Diffusive Flow in a Large-Pore Graphite

Report describing an "investigation of steady-state counter-flow of gases in a large pore graphite" by exposing it to streams of helium and argon.
Date: 1961
Creator: Evans, R. B., III; Truitt, J. & Watson, G. M.
System: The UNT Digital Library
Sulfex Process: Engineering-Scale Semicontinuous Decladding of Unirradiated Stainless Steel-Clad UO2 and UO2-ThO2 (open access)

Sulfex Process: Engineering-Scale Semicontinuous Decladding of Unirradiated Stainless Steel-Clad UO2 and UO2-ThO2

An engineering-scale demonstration of the Sulfex process indicated that semi-continuous decladding of unirradiated stainless steel-clad UO2 or U02ThO2 fuels is feasible.
Date: April 4, 1961
Creator: Finney, B. C. & Hannaford, B. A.
System: The UNT Digital Library