An Engineering Test Program to Investigate a Loss of Coolant Accident (open access)

An Engineering Test Program to Investigate a Loss of Coolant Accident

From preface: "The purpose of this report is to present an engineering test program for investigating a loss of coolant accident for a pressurized water-cooled and moderated reactor system."
Date: October 1964
Creator: Wilson, T. R.; Hauge, O. M.; Matheney, G. B. & Homer, G. B.
System: The UNT Digital Library
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
System: The UNT Digital Library
Chemical Coolants for Machining Uranium in the Presence of Trace Amounts of Chloride (open access)

Chemical Coolants for Machining Uranium in the Presence of Trace Amounts of Chloride

Discussion of laboratory tests to reduce uranium corrosion.
Date: October 14, 1964
Creator: Sprague, T. P.; Googin, J. M. & Phillips, L. R.
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.
System: The UNT Digital Library
The Effect of Deionized Water on the Reactor Effluent Activities: Part 2 - Zirconium and Aluminum Clad Fuel (open access)

The Effect of Deionized Water on the Reactor Effluent Activities: Part 2 - Zirconium and Aluminum Clad Fuel

Report containing experimental data testing the hypothesis that aluminum reactor tubes were "the site of most radioisotope production in the deionized water cooled system" and that zirconium tubes provided "only nominal participation" (p. 2).
Date: October 1964
Creator: Silker, W. B. & Thomas, C. W.
System: The UNT Digital Library
The H-4, H-5, and H-6 Irradiation Experiments: Irradiation of N-Reactor Graphite, Interim Report Number 1 (open access)

The H-4, H-5, and H-6 Irradiation Experiments: Irradiation of N-Reactor Graphite, Interim Report Number 1

Report regarding an experimental program by Hanford Laboratories' in order "to determine the long-term irradiation behavior of the graphite used as the moderator in N-Reactor. The primary objectives of the program are to provide data for predictions of the distortion of the N-Reactor moderator and the stress conditions which could arise from the difference in the the rate and extent of contraction between the transverse and parallel orientations of the graphite bars" (p. 1).
Date: October 1964
Creator: Helm, J. W.
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.
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.
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.
System: The UNT Digital Library
Condensation of Metal Vapors: Mercury and the Kinetic Theory of Condensation (open access)

Condensation of Metal Vapors: Mercury and the Kinetic Theory of Condensation

Report issued by the Argonne National Laboratory discussing condensation theories of metal vapors. As stated in the introduction, "the objectives of this research then are critical analysis of condensation theories and data for metal vapors and experimental evaluation of the resistance to condensation for a representative metal such as mercury" (p. 18). This report includes tables, illustrations, and photographs.
Date: October 1964
Creator: Wilhelm, Donald J.
System: The UNT Digital Library
Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1964 - September 1, 1964 (open access)

Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1964 - September 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: October 1, 1964
Creator: Hardy, Edward P., Jr. & Rivera, Joseph
System: The UNT Digital Library