Serial/Series Title
Decade
Month
14 Matching Results
Results open in a new window/tab.
Results:
1 - 14 of
14
Chemical Technology Division Annual Progress Report: for Period Ending May 31, 1969
Report documenting the ongoing research and development of the Oak Ridge National Laboratory's Chemical Technology Division.
Date:
October 1969
Creator:
Oak Ridge National Laboratory. Chemical Technology Division.
System:
The UNT Digital Library
Development and Demonstration of an Ion-Exchange Process for Kilogram-Scale Production of High Purity Promethium
Report regarding "the development of a process suitable for large-scale separation of highly purified promethium from the trivalent fission product rare earth mixture" (p. 3).
Date:
October 1963
Creator:
Wheelwright, E. J. (Earl J.) & Roberts, F. P.
System:
The UNT Digital Library
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
Evaluation of Ultimate Disposal Methods for Liquid and Solid Radioactive Wastes: Part 2, Conversion to Solid by Pot Calcination
Economic and hazards calculation of pot calcination of Purex and Thorex wastes.
Date:
October 16, 1961
Creator:
Perona, J. J.; Bradshaw, R. L.; Roberts, J. T. & Blomeke, J. O.
System:
The UNT Digital Library
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
Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1965 - September 1, 1965
Report documenting radioactive fallout across the world, including material in the atmosphere, on land, and that has deposited into food and water supplies.
Date:
October 1, 1965
Creator:
Hardy, Edward P., Jr. & Rivera, Joseph
System:
The UNT Digital Library
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
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
A Method for Beta-Gamma Hand and Shoe Counting Under Varying Background Conditions
Report containing a method for beta-gamma counting of hands, shoes, and clothing via an instrument that employs scintillation detectors and solid-state circuits.
Date:
October 1963
Creator:
Spear, W. G.
System:
The UNT Digital Library
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
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
Specifications for Swage Compacted, Mixed Oxide (UO2-PuO2), Fuel Elements for the Plutonium Recycle Test Reactor (MARK I-M)
Report containing the dimensions, materials, and fabrication details for swage compacted, mixed oxide (UO2-PuO2), fuel elements for the Plutonium Recycle Test Reactor (MARK I-M).
Date:
October 1963
Creator:
Hanford Atomic Products Operation
System:
The UNT Digital Library
Specifications for Vibrationally Compacted, Mixed Oxide (UO2-PuO2), Fuel Elements for the Plutonium Recycle Test Reactor (MARK I-L)
Report describing the dimensions, materials, and fabrication of vibrationally compacted, mixed oxide (UO2-PuO2) fuel elements for the Plutonium Recycle Test Reactor (MARK I-L). Appendix begins on page 38.
Date:
October 1, 1963
Creator:
Hanford Atomic Products Operation
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
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