The HASL Bone Program 1961-1964 (open access)

The HASL Bone Program 1961-1964

Report documenting the measuring of strontium-90 levels contained in the bones of children and adults of various age brackets across the United States.
Date: August 16, 1965
Creator: Rivera, Joseph & Harley, John H.
System: The UNT Digital Library
Applied Health Physics Annual Report for 1963 (open access)

Applied Health Physics Annual Report for 1963

Report issued by the Oak Ridge National Laboratory discussing work and progress made by the Health and Physics Division during 1963. Instrumentation, personnel monitoring, and laboratory monitoring is presented. This report includes maps, tables, illustrations, and photographs.
Date: August 1964
Creator: Morgan, K. Z.; Davis, D. M.; Hart, J. C.; Abee, H. H.; Gupton, E. D. & Warden, A. D.
System: The UNT Digital Library
Distribution of Uranium at Low Acid : Low Uranium Concentrations into 4-1/2 Percent TBP-AMSCO (open access)

Distribution of Uranium at Low Acid : Low Uranium Concentrations into 4-1/2 Percent TBP-AMSCO

Report wherein acid free uranyl nitrate hexahydrate was distributed into 4-1/2 percent TBP-Amsco 125-90W and combined with various concentrations of acid in order to study the distribution of uranium and hydrolysis effects.
Date: August 23, 1956
Creator: Andelin, Robert L.; Anderson, Edward L. & McVey, W. H.
System: The UNT Digital Library
Maintenance of ETR Coolant (open access)

Maintenance of ETR Coolant

Report describing the maintenance system in place for the coolant system of an Engineering Test Reactor (ETR).
Date: August 15, 1958
Creator: Haas, F. C.
System: The UNT Digital Library
Homogeneous Reactor Project Quarterly Progress Report: February-April 1959 (open access)

Homogeneous Reactor Project Quarterly Progress Report: February-April 1959

Report documenting the ongoing research and developments of the Oak Ridge National Laboratory's Homogeneous Reactor Project.
Date: August 8, 1959
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
A Computer Code (CDC 1604A or IBM 7090) for Calculating the Cost of Shipping Spent Reactor Fuels as a Function of Burnup, Specific Power, Cooling Time, Fuel Composition, and Other Variables (open access)

A Computer Code (CDC 1604A or IBM 7090) for Calculating the Cost of Shipping Spent Reactor Fuels as a Function of Burnup, Specific Power, Cooling Time, Fuel Composition, and Other Variables

Report presenting the calculation of the costs incurred in shipping irradiated uranium-containing fuel elements. A computer code that designs a cask and calculates the shipping costs is presented. By use of the code, shipping costs were calculated for typical reactor fuels.
Date: August 1964
Creator: Salmon, Royes
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
Consolidated Nuclear Steam Generator for Merchant Ship Application: A Conceptual Design (open access)

Consolidated Nuclear Steam Generator for Merchant Ship Application: A Conceptual Design

Report concerning the economic feasibility of pressurized water reactors for use aboard merchant ships. This includes conceptual designs and work remaining for the future of a Pressurized Water Reactor.
Date: August 1962
Creator: Babcock & Wilcox Company
System: The UNT Digital Library
Progress in Nondestructive Testing: A Summary of Hanford Achievements in These Programs Under General Electric, 1952 - 1964 (open access)

Progress in Nondestructive Testing: A Summary of Hanford Achievements in These Programs Under General Electric, 1952 - 1964

Report discussing the development of Hanford Laboratories' nondestructive testing programs and a summary of their results. Programs include AlSi fuel testing, N-Reactor fuel testing, and reactor research and development.
Date: August 1964
Creator: Walker, R. A. & Russell, J. T.
System: The UNT Digital Library
Hazards Summary Report for the Hanford Plutonium Critical Mass Laboratory (open access)

Hazards Summary Report for the Hanford Plutonium Critical Mass Laboratory

Report that summarizes the potential hazards of the Hanford Critical Mass Laboratory and presents operation procedures which will limit the probability of a nuclear accident. The report also outlines the planned experimental program, descriptions of the facility, and the administration of nuclear safety in the laboratory.
Date: August 1, 1960
Creator: Reardon, W. A.; Clayton, E. D.; Brown, C. L.; Masterson, R. H.; Powell, T. J.; Richey, C. R. et al.
System: The UNT Digital Library
Dissolution of Power Reactor Fuel Cores (open access)

Dissolution of Power Reactor Fuel Cores

Report discussing the dissolution of simulated fuel cores. Equipment and procedures are discussed along with significant characteristics of the core materials.
Date: August 26, 1960
Creator: Blaine, H. T.
System: The UNT Digital Library
Calculated Equilibrium Distributions for the Uranyl Nitrate - Tributyl Phosphate - Dilute Nitric Acid System for Temperatures Between 25 and 75 C (open access)

Calculated Equilibrium Distributions for the Uranyl Nitrate - Tributyl Phosphate - Dilute Nitric Acid System for Temperatures Between 25 and 75 C

Report discussing the "equilibrium uranium distribution between an aqueous nitric acid solution and a 30 per cent by volume solution of tributyl phosphate in a hydrocarbon diluent" (p. 2). This includes the necessary equations.
Date: August 12, 1960
Creator: Wilburn, N. P.
System: The UNT Digital Library
Calculated Costs of Fabrication of Plutonium-Enriched Fuel Elements (open access)

Calculated Costs of Fabrication of Plutonium-Enriched Fuel Elements

Report regarding the study of the calculated costs of fabricating plutonium-enriched fuel elements for Hanford Laboratories' Plutonium Recycle Program. Topics include descriptions of the process, design study of plants that use U235 and plutonium enriched fuel, and estimates of costs.
Date: August 1962
Creator: Hanthorn, H. E.
System: The UNT Digital Library
In-Reactor Monitoring of Zircaloy-2 Plutonium Recycle Test Reactor Pressure Tubes: Part 2, May and June, 1962 (open access)

In-Reactor Monitoring of Zircaloy-2 Plutonium Recycle Test Reactor Pressure Tubes: Part 2, May and June, 1962

Report containing the results of a two year program wherein the 85 zircaloy-2 pressure tubes in Hanford Laboratories' Plutonium Recycle Test Reactor (PRTR) were monitored. Experimental procedures and results are described.
Date: August 1962
Creator: Doman, D. R. & Pankaskie, P. J.
System: The UNT Digital Library
Protective Clothing Monitoring System (open access)

Protective Clothing Monitoring System

Report describing the development and installation of an automated conveyor-type laundry system for the purpose of monitoring laboratory clothing for beta-gamma contamination.
Date: August 1, 1963
Creator: Rankin, M. O. & Spear, W. G.
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
The High Flux Isotope Reactor: Volume 2, Selected Construction Drawings (open access)

The High Flux Isotope Reactor: Volume 2, Selected Construction Drawings

Report containing a series of drawings detailing the Oak Ridge National Laboratory's high flux isotope reactor, its surroundings, and its systems.
Date: August 1964
Creator: Binford, F. T.; Cramer, E. N. & Cramer, E. N.
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
Molten-Salt Reactor Program Semiannual Progress Report, February 28, 1971 (open access)

Molten-Salt Reactor Program Semiannual Progress Report, February 28, 1971

Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program.
Date: August 1971
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
Scintillation Spectrometry Gamma-Ray Catalogue: Volume 2 (open access)

Scintillation Spectrometry Gamma-Ray Catalogue: Volume 2

Gamma-Ray Spectrum diagrams.
Date: August 1964
Creator: Heath, R. L.
System: The UNT Digital Library
The Beta-Gamma Surface Dosage Rate from Natural Uranium (open access)

The Beta-Gamma Surface Dosage Rate from Natural Uranium

From summary: "Report discussing the beta-gamma dosage rate at the surface of a natural uranium disc. Measurements were taken using a Ryerson electrometer and an extrapolation ionization chamber."
Date: August 22, 1949
Creator: Kalmon, Ben
System: The UNT Digital Library
Radiation Damage in Boron Carbide (open access)

Radiation Damage in Boron Carbide

From introduction: "Report describing the study of radiation damage in boron carbide with an integrated thermal neutron flux of 3x10^20 neutrons/cm² in the Materials Testing Reactor (MTR)."
Date: August 18, 1953
Creator: Tucker, Charles W., Jr. & Senio, Peter
System: The UNT Digital Library
Stress Corrosion Cracking in Uranium-Molybdenum Alloys (open access)

Stress Corrosion Cracking in Uranium-Molybdenum Alloys

Investigation conducted to determine the cause of cracking, during tension, on the surface of tensile specimens of uranium-molybdenum alloys.
Date: August 12, 1963
Creator: Pridgeon, J. W.
System: The UNT Digital Library
Nuclear Superheat Quarterly Project Report: Eleventh Quarter, January-March 1962 (open access)

Nuclear Superheat Quarterly Project Report: Eleventh Quarter, January-March 1962

From introduction: "This is the eleventh of a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date: August 1962
Creator: Pennington, R. T.
System: The UNT Digital Library