Analytical Chemistry Division Annual Progress Report for Period Ending November 15, 1964 (open access)

Analytical Chemistry Division Annual Progress Report for Period Ending November 15, 1964

Report issued by the Oak Ridge National Laboratory discussing progress and work conducted by the Analytical Chemistry Division. Instrumentation, analytical methods, reactor projects, service analysis, and special research is presented. This report includes tables, illustrations, and photographs.
Date: January 1965
Creator: Kelley, M. T.; Susano, C. D. & Fisher, D. J.
System: The UNT Digital Library
Hanford Radiological Sciences Research and Development Annual Report for 1963 (open access)

Hanford Radiological Sciences Research and Development Annual Report for 1963

Report regarding ongoing research and development undertaken at Hanfdord Laboratories' physics and instruments laboratory and chemical laboratory.
Date: January 1964
Creator: Gamertsfelder, C. C. & Green, J. K.
System: The UNT Digital Library
The Facility 350 Helium-Atmosphere System (open access)

The Facility 350 Helium-Atmosphere System

Report describing the helium atmosphere system in the Argonne National Laboratory's Facility 350. The atmosphere's ability to remove moisture, oxygen, and other impurities, how the atmosphere is purified, and experimental data regarding the use of activated carbon to absorb oxygen from helium are discussed.
Date: December 1962
Creator: Mayfield, R. M.; Tope, W. G. & Shuck, A. B.
System: The UNT Digital Library
High-Density Concrete for Gamma and Neutron Attenuation (open access)

High-Density Concrete for Gamma and Neutron Attenuation

Report issued by the Oak Ridge National Laboratory discussing the development of a high-density concrete. As stated in the abstract, "the basic approach to high-density concrete mix design is reviewed to show that theoretical calculations for concrete mixes do give results that are reliable" (p. 1). This report includes tables, illustrations, and photographs.
Date: March 1965
Creator: Northup, T. E.
System: The UNT Digital Library
Molten-Salt Reactor Program Semiannual Progress Report for Period Ending February 28, 1965 (open access)

Molten-Salt Reactor Program Semiannual Progress Report for Period Ending February 28, 1965

Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Molten-Salt Reactor Program. Progress of operations, construction, engineering analysis, and development is presented. This report includes tables, illustrations, and photographs.
Date: June 1965
Creator: Briggs, R. B.
System: The UNT Digital Library
Oak Ridge Analytical Chemistry Division Annual Progress Report: 1963 (open access)

Oak Ridge Analytical Chemistry Division Annual Progress Report: 1963

Report containing the ongoing research and development of the Oak Ridge National laboratory's Analytical Chemistry Division.
Date: 1964-12~
Creator: Oak Ridge National Laboratory. Analytical Chemistry Division.
System: The UNT Digital Library
Physics Division Annual Progress Report, January 31, 1964 (open access)

Physics Division Annual Progress Report, January 31, 1964

Report containing ongoing research and development of the Oak Ridge National Laboratory's Physics Division.
Date: June 1964
Creator: Oak Ridge National Laboratory. Physics Division.
System: The UNT Digital Library
Health Physics Division Annual Progress Report, July 31, 1961 (open access)

Health Physics Division Annual Progress Report, July 31, 1961

Report documenting research and developments made by the Health Physics Division of the Oak Ridge National Laboratory.
Date: October 31, 1961
Creator: Oak Ridge National Laboratory. Health Physics Division.
System: The UNT Digital Library
Chemical Technology Division Annual Progress Report: for Period Ending June 30, 1962 (open access)

Chemical Technology Division Annual Progress Report: for Period Ending June 30, 1962

Report issued by Oak Ridge National Laboratory that discusses progress and work performed by the Chemical Technology Division.
Date: September 21, 1962
Creator: Oak Ridge National Laboratory. Chemical Technology Division.
System: The UNT Digital Library
Gas-Cooled Reactor Project Semiannual Progress Report: September 1963 (open access)

Gas-Cooled Reactor Project Semiannual Progress Report: September 1963

Report documenting the design and testing progress of the Oak Ridge National Laboratory's Gas-Cooled Reactor Program.
Date: January 29, 1964
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
Argonne National Laboratory Metallurgy Division Annual Report: 1963 (open access)

Argonne National Laboratory Metallurgy Division Annual Report: 1963

Annual report issued by the Argonne National Laboratory discussing work conducted by the Metallurgy Division during 1963 including progress related to experiments, programs, and studies. This report includes tables, illustrations, and photographs.
Date: 1964
Creator: Foote, Frank G.; Chiswik, Haim H. & Macherey, Robert E.
System: The UNT Digital Library
Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 1 - The Mark 1-G (open access)

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

Report describing "[t]he fabrication of of the first aluminum-plutonium spike enrichment fuel elements for the Plutonium Recycle Test Reactor (PRTR) at Hanford" Laboratory (p. 2).
Date: March 1961
Creator: Freshley, M. D.
System: The UNT Digital Library
Pneumatic Injection Casting of Aluminum-Plutonium Fuel Elements (open access)

Pneumatic Injection Casting of Aluminum-Plutonium Fuel Elements

This report summarizes only that portion of the injection-casting experiments in which the castings were made with air pressure.
Date: April 1961
Creator: Koler, R. K.
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
Steady Darcian Transport of Fluids in Heterogeneous Partially Saturated Porous Media: Part 2, the Computer Program (open access)

Steady Darcian Transport of Fluids in Heterogeneous Partially Saturated Porous Media: Part 2, the Computer Program

The subject of this report is the generalized computer program written to solve problems involving steady fluid flow through heterogeneous, partially-saturated porous media.
Date: May 20, 1964
Creator: Nelson, R. William
System: The UNT Digital Library
Proceedings of the Thorium Fuel Cycle Symposium, 1962: Book 1, Sessions 1-3 (open access)

Proceedings of the Thorium Fuel Cycle Symposium, 1962: Book 1, Sessions 1-3

From foreword: This report contains thirty-three papers that were presented at a symposium regarding the use of thorium and uranium-233 in nuclear reactors.
Date: 1963?
Creator: unknown
System: The UNT Digital Library
Plowshare Symposium, 1964: Engineering with Nuclear Explosives (open access)

Plowshare Symposium, 1964: Engineering with Nuclear Explosives

From foreword: The major objective of the symposium is informing engineers in industry, military, educational institutions, and in government agencies throughout the world of the current state-of-the-art nuclear explosives from an engineering standpoint.
Date: 1964?
Creator: unknown
System: The UNT Digital Library