Serial/Series Title
Decade
Year
Month
48 Matching Results
Results open in a new window/tab.
Results:
1 - 24 of
48
next
Geophysical Seismic Evaluation Study at Hanford
From introduction: "In June, 1963, a geophysical research program was conducted at Hanford to determine the feasibility and desirability of using seismic methods in geohydrologic studies. Detection and delineation were desired of seven different geological features that in some sites affect the movement of liquid radioactive wastes discharged to the ground."
Date:
December 1964
Creator:
Brown, Ruth E. & Raymond, John R.
System:
The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: July 1 - September 30, 1964
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
Date:
November 13, 1964
Creator:
Aerojet-General Corporation
System:
The UNT Digital Library
Nuclear Cratering Experience at the Pacific Proving Grounds
Observation of the long-term effects of weathering on 10 nuclear craters over periods as long as 12 years.
Date:
November 10, 1964
Creator:
Circeo, Louis J., Jr. & Nordyke, Milo D.
System:
The UNT Digital Library
Evaporation of Iron-, Nickel-, and Cobalt-Base Alloys at 760 to 980°C in High Vacuums
Report issued by the Oak Ridge National Laboratory discussing the evaporation of alloys in high vacuums. As stated in the introduction, "the investigation encompasses measurements of the evaporation rates, identification of the evaporating elements, and correlation of these measurements to the alloy composition for specimens in both the polished and oxidized conditions" (p. 2). This report includes tables, illustrations, and photographs.
Date:
November 1964
Creator:
Bourgette, D. T.
System:
The UNT Digital Library
Irradiation Testing of Fuel for Core B of the Enrico Fermi Fast Breeder Reactor
Report issued by the Oak Ridge National Laboratory discussing irradiation testing of fast breeder reactors. As stated in the introduction, "it is the purpose of this report to describe the irradiation studies carried out in support of the Core B fuel element development program" (p. 3). This report includes tables, illustrations, and photographs.
Date:
November 1964
Creator:
Thurber, W. C.; McQuilkin, F. R.; Long, E. L., Jr. & Osborne, M. F.
System:
The UNT Digital Library
Molten-Salt Reactor Program Semiannual Progress Report for Period Ending July 31, 1964
Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Molten-Salt Reactor Program. Descriptions of design, construction, and experimental progress is presented. This report includes tables, illustrations, and photographs.
Date:
November 1964
Creator:
Briggs, R. B.
System:
The UNT Digital Library
PRTR second generation shim assembly
From introduction: "This document discusses the design, fabrication, assembly, and testing of a second generation shim rod assembly, and testing of a second generation shim rod assembly prototype for use in the Plutonium Recycle Test Reactor."
Date:
November 1964
Creator:
Rasmussen, D. E.
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
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
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
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
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
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.
System:
The UNT Digital Library
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.
System:
The UNT Digital Library
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.
System:
The UNT Digital Library
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.
System:
The UNT Digital Library
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.
System:
The UNT Digital Library
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.
System:
The UNT Digital Library
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
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
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
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
Recovery of Aluminum Nitrate Nonahydrate from Redox Acid Waste, Part 1: Computer Study
Report describing an analog computer simulation of a counter-current crystallization process for use in the recovery of aluminum nitrate nonahydrate from redox acid waste
Date:
July 1964
Creator:
Godfrey, W. L. & Benham, R. D.
System:
The UNT Digital Library