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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

Description: 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.

Measurement of α, the Ratio of the Neutron Capture Cross Section to the Fission Cross Section, for ²³⁵U in the Energy Region from 3.25 eV to 1.8 keV

Description: Report issued by the Oak Ridge National Laboratory discussing techniques to obtain measurements of alpha for enriched uranium. Descriptions of equipment and experiments used to obtain alpha are presented. This report includes tables, and illustrations.
Date: April 1965
Creator: deSussure, G.; Weston, L. W.; Gwin, R.; Russell, J. E. & Hockenbury, R. W.

Computer Programs Using Zonal Harmonics for Magnetic Properties of Current Systems with Special Reference to the IBM 7090

Description: Report that "discusses the magnetic vector and scalar potentials, magnetic field components and their derivatives, and flux linkage for single current systems, and the mutual inductance, forces and torques between two such systems, whose axes are coplanar but not necessarily coincident" (p. 1).
Date: December 4, 1962
Creator: Garrett, M. W.

The Hanford Isotopes Production Plant Engineering Study

Description: Report presenting the conceptual design, estimates of capital and operating costs, and details of the operation of a plant "capable of high volume production of encapsulated heat sources" (p. 3) of radioisotopes Sr90, Cs137, Ce144, and Pm147.
Date: July 1963
Creator: La Riviere, J. R.; Michels, L. R.; Riches, H. C.; Rohrmann, C. A.; Smith, C. W. & Swift, W. H.

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

Description: 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.

6144-Channel Time-of-Flight Analyzer

Description: 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.

Preliminary Solution Critical Experiments for the High-Flux Isotope Reactor

Description: Report containing experiments conducted at the Oak Ridge National Laboratory's Critical Experiments Facility. These experiments involved "determining the critical parameters of the assembly with varying amounts of neutron absorber in the D20 reflector, measuring the relative neutron flux distribution for various conditions of reflector poison and fissile solution concentration, determining the ratio of the absolute thermal-neutron flux in the center of the assembly to the power in the fissile solution , and determining the effect on reactivity of reducing the hydrogen density in the central region of the assembly" (p. 1).
Date: June 12, 1963
Creator: Fox, J. K.; Magnuson, D. W. & Gilley, L. W.