Serial/Series Title

States

Irradiation Performance of Thoria-Urania Fuel Materials: Quarterly Technical Report, Number 2, October - December 1964 (open access)

Irradiation Performance of Thoria-Urania Fuel Materials: Quarterly Technical Report, Number 2, October - December 1964

From introduction: "Complete exploitation of the advantages of thorium as a fertile material in thermal and particular resonant spectrum reactors has been inhibited by the lack of quantitative physical property data for thoria and thoria-urania fuels."
Date: October 1964
Creator: Babcock & Wilcox Company
Object Type: Report
System: The UNT Digital Library
Plutonium Recycle Critical Facility: Final Safeguards Analysis Supplements (open access)

Plutonium Recycle Critical Facility: Final Safeguards Analysis Supplements

Report containing supplementary material for "Plutonium Recycle Critical Facility, Final Safeguards Analyses." This material expands upon previously supplied safety information and resolves previously unreviewed safety questions. Appendix begins on page A.1.
Date: October 1964
Creator: Swanberg, F.
Object Type: Report
System: The UNT Digital Library
Solid State Division Annual Progress Report, May 31, 1964 (open access)

Solid State Division Annual Progress Report, May 31, 1964

Report containing ongoing research and development of the Solid State Division of the Oak Ridge National Laboratory.
Date: October 1964
Creator: Oak Ridge National Laboratory. Solid State Division.
Object Type: Report
System: The UNT Digital Library
Thermodynamic Calculations Relating to Chloride Volatility Processing of Nuclear Fuels: [Part] 2. The Capacity of Chlorine for Transporting Plutonium Tetrachloride Vapor During Reaction of U3O8-PuO2 with Carbon Tetrachloride (open access)

Thermodynamic Calculations Relating to Chloride Volatility Processing of Nuclear Fuels: [Part] 2. The Capacity of Chlorine for Transporting Plutonium Tetrachloride Vapor During Reaction of U3O8-PuO2 with Carbon Tetrachloride

Report issued by the Oak Ridge National Laboratory discussing thermodynamic calculations of nuclear fuels. As stated in the introduction, "the equations developed in this report could be used to calculate the capacity of chlorine for transporting plutonium tetrachloride" (p. 2). This report includes tables, and illustrations.
Date: October 1964
Creator: Gens, T. A.
Object Type: Report
System: The UNT Digital Library
Zirconium Processing Capability of the Idaho Chemical Processing Plant (open access)

Zirconium Processing Capability of the Idaho Chemical Processing Plant

Report discussing a hydrofluoric acid dissolution process that allows the processing of zirconium- or Zircaloy-clad zirconium-uranium fuels.
Date: October 1964
Creator: Bower, J. R.
Object Type: Report
System: The UNT Digital Library
6144-Channel Time-of-Flight Analyzer (open access)

6144-Channel Time-of-Flight Analyzer

Report describing a 6144-channel analyzer designed and built for the purpose of analyzing time-of-flight during studies of slow neutron scattering at Hanford Laboratories. This includes descriptions of the analyzer, its logic and circuits, and its test mode.
Date: September 1964
Creator: Walker, R. A. & Russell, J. T.
Object Type: Report
System: The UNT Digital Library
Analog Computer Simulation of a Pulsed Extraction Column (open access)

Analog Computer Simulation of a Pulsed Extraction Column

Report describing "computer techniques used in the simulation and parameter determination, how the data were prepared for inclusion in the computer simulation, (and) methods used in presenting the results" (p. 3-4).
Date: September 1964
Creator: Benham, R. D. & Wilburn, N. P.
Object Type: Report
System: The UNT Digital Library
Analog Simulation of the Hanford N-Reactor Plant, Part 1: Description of the Overall Simulation Model (open access)

Analog Simulation of the Hanford N-Reactor Plant, Part 1: Description of the Overall Simulation Model

Report that describes Hanford Laboratories' overall N-Reactor plant simulation model and its use to study the characteristics of the plant, plant operational procedures, and the effects of plant, operator, and control system malfunctions.
Date: September 1, 1964
Creator: Swanson, C. D.; Coughren, K. D.; Dionne, P. J. & Thieme, G. G.
Object Type: Report
System: The UNT Digital Library
Full Power and Limited Endurance Test of the ML-1 Nuclear Power Plant (ANSOP 16625A) (open access)

Full Power and Limited Endurance Test of the ML-1 Nuclear Power Plant (ANSOP 16625A)

Report presenting "[t]he results of performance analyses of the ML-1 nuclear power plant based on the test data obtained during ANSOP 16625A" (p. v).
Date: September 1964
Creator: Aerojet-General Corporation
Object Type: Report
System: The UNT Digital Library
Gas-Cooled Fast Reactor Concepts (open access)

Gas-Cooled Fast Reactor Concepts

Report describing the performance characteristics of gas-cooled fast reactors, which compare well with those of sodium-cooled fast reactors. With oxide fuel and helium, CO2, and SO2 coolant at pressures of 1000 to 1500 psia, the reactors have slightly higher breeding ratios than comparable sodium-cooled reactors.
Date: September 1964
Creator: Oak Ridge National Laboratory. Reactor Division. Gas-Cooled Reactor Project.
Object Type: Report
System: The UNT Digital Library
The Graetz Problem in Cocurrent-Flow, Double-Pipe, Heat Exchangers (open access)

The Graetz Problem in Cocurrent-Flow, Double-Pipe, Heat Exchangers

Report showing "that the Graetz Problem pertaining to the cocurrent-flow, double-pipe, heat exchanger can be studied analytically by extensions of familiar mathematical techniques" (p. 7).
Date: September 1964
Creator: Stein, Ralph P.
Object Type: Report
System: The UNT Digital Library
The H-3 Irradiation Experiment: Irradiation of Experimental Gas Cooled Reactor Graphite, Number 2 (open access)

The H-3 Irradiation Experiment: Irradiation of Experimental Gas Cooled Reactor Graphite, Number 2

Report documenting "the long-term irradiation stability of the graphite used as the moderator in the Experimental Gas Cooled Reactor (EGCR) at Oak Ridge" (p. 1) by irradiating capsules at the General Electric Test Reactor. This includes the design and construction of the experiment, experiment procedures, and results of irradiation. Appendices begin on page 83.
Date: September 1964
Creator: Helm, J. W.
Object Type: Report
System: The UNT Digital Library
Solidification of High-Level Radioactive Fuel Reprocessing Wastes by Spray and Pot Calcination: Hot-Cell Pilot Plant Studies (open access)

Solidification of High-Level Radioactive Fuel Reprocessing Wastes by Spray and Pot Calcination: Hot-Cell Pilot Plant Studies

Report regarding the calcination of full level Purex and Redox waste carried out "in a remotely operated pilot plant consisting of a radiant-heat spray calciner and a pot calciner and their associated off-gas equipment" (p. 4). This contains details of the calcination, effects on the waste, and difficulties encountered.
Date: September 1964
Creator: Allemann, R. T.; Roberts, F. P. & Upson, U. L.
Object Type: Report
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.
Object Type: Report
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
Object Type: Report
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.
Object Type: Report
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.
Object Type: Report
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.
Object Type: Report
System: The UNT Digital Library
X-Ray Fluorescence Tables: Program Description (open access)

X-Ray Fluorescence Tables: Program Description

Report discussing the mechanics of X-Ray and COMBO computer programs.
Date: July 20, 1964
Creator: Amsbury, W. P.; Lee, W. W.; Rowan, J. H. & Walden, G. E.
Object Type: Report
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
Object Type: Report
System: The UNT Digital Library
Fundamentals in the Operation of Nuclear Test Reactors: Volume 3 Engineering Test Design and Operation (open access)

Fundamentals in the Operation of Nuclear Test Reactors: Volume 3 Engineering Test Design and Operation

Engineering test reactor design and operation.
Date: July 1964
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Health and Safety Laboratory Fallout Program Quarterly Summary Report: March 1, 1964 - June 1, 1964 (open access)

Health and Safety Laboratory Fallout Program Quarterly Summary Report: March 1, 1964 - June 1, 1964

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: July 1, 1964
Creator: Hardy, Edward P., Jr.; Rivera, Joseph & Collins, William R., Jr.
Object Type: Report
System: The UNT Digital Library
Molten-Salt Reactor Program Semiannual Progress Report, January 31, 1964 (open access)

Molten-Salt Reactor Program Semiannual Progress Report, January 31, 1964

Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program.
Date: July 1964
Creator: Oak Ridge National Laboratory
Object Type: Report
System: The UNT Digital Library
Performance Characteristics of a Liquid Metal MHD Generator (open access)

Performance Characteristics of a Liquid Metal MHD Generator

Report issued by the Argonne National Laboratory discussing the performance of magnetohydrodynamic generators. As stated in the abstract, "an experimental study was made of the performance characteristics of a liquid metal MHD generator utilizing single-phase sodium-potassium and two-phase sodium-potassium-nitrogen fluids. The purpose of this study was to compare the generator performance with theory for single-phase flow and to determine the effects of the introduction of the gaseous phase on the generator output and efficiency" (p. 9). This report includes tables, illustrations, and photographs.
Date: July 1964
Creator: Petrick, Michael & Lee, Kung-You
Object Type: Report
System: The UNT Digital Library