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The Relation of Flash Point to Vapor Pressure

Description: Report outlining the relation of the ASTM flash point of oil, a rough measure of the safety of storage and use when oil sparks, to other directly determinable physical properties. Summarizes the data on vapor pressures, boiling curves, and flash points of various hydrocarbon diluents.
Date: February 24, 1955
Creator: Burger, L. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Quarterly Report- July, August, September 1958 Plutonium Fuels Development Plutonium Metallurgy Operation

Description: Examination of Al- 1.65w/o Pu and Al- 12 w/o Si- 1.65 w/o Pu capsules irradiated 55- 60% burnout of the plutonium atoms revealed a 1.4% volume increase and no apparent microstructural changes. A four rod cluster containing Al-8 w/o Pu and Al-12 w/o Si-8 w/o Pu alloy cores is currently under irradiation in Loop 3 of KE Reactor at a water temperature of approximately 230C. A second cluster has been fabricated an is scheduled for charging late in 1958. Two seven-rod clusters for irradiation in KE… more
Date: February 24, 1959
Creator: Wick, O.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Zirflex- Interim Development Summary

Description: The processing of spent fuels from nuclear power and propulsion reactors is planned by Hanford Atomic Products Operation as part of the Atomic Energy Commission's interim processing scheme. The spent nuclear fuels have cores of UO2, U, or alloys of U-Mb, U-Al, or U-Zr clad in either stainless steel, aluminum, or Zircaloy. This report discusses only the Zircaloy-clad fuels and the applications of the Zirflex Process for dissolution. Zirflex chemical flow sheets are presented as developed by pilo… more
Date: June 24, 1959
Creator: Platt, A. M. & Cooley, C. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary Chemical Flowsheets for the Decladding and Dissolution of Non-Production Fuels

Description: This document presents preliminary chemical flowsheets for cladding and core dissolution of zircaloy-clad uranium dioxide and stainless steel-clad uranium-molybdenum non-production fuels. These preliminary flowsheets together with existing process flowsheets should be adequate for process development in the currently forecast non-production fuels dissolution facility.
Date: July 24, 1959
Creator: Harmon, M. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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DC Bridge NPR Horizontal Rod Counting

Description: This report is a summary of work done for system development on the NPR ball safety backup for the horizontal rods. This phase of the system development is limited to discussion of the horizontal rod counting circuitry utilizing a direct current bridge network.
Date: July 24, 1959
Creator: {{{name}}}
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of a Nuclear Incident in a Redox Dissolver

Description: Since the start of E-metal processing in December, 1958, critical mass control in the Redox dissolvers has been provided by a combination of administrative controls, revised dissolver charging procedures, and new dissolving processes and operation control procedures. These were all based on a maximum allowable charge of E-Metal to the dissolvers which was equivalent to 45 percent of the minimum critical mass.
Date: August 24, 1959
Creator: Neely, V. I.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Eddy Current Ultrasonic Transducer

Description: In the field of nondestructive testing the ultrasonic test method is used extensively. In this method ultrasonic energy generated by a transducer is caused to enter the test specimen. The effect on the transducer is cause to enter the test specimen. The effect on the transmission or reflection of the ultrasonic energy by differing test specimen structure is used as an indirect measure of test specimen characteristics.
Date: August 24, 1959
Creator: Libby, Hugo L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Eurochemic Questions -- Preliminary Report

Description: The referenced memo asked several questions on the operation of the Purex Plant which are of interest to the Eurochemic personnel. These questions are answered below. 1. A qualitative description of the nitric acid recovery systems is desired -- flow of materials, number of pieces of equipment, etc.
Date: August 24, 1959
Creator: Geier, R. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development and Testing of an Improved Agitator for the Redox and Purex Separations Plants

Description: Relatively frequent agitator failures in HAPO Separations Plants have interfered with process continuity, contributed to process difficulties, and resulted in considerable maintenance expense. Predominantly the failures have been because of gear-reduction drive unit break-down or because of metallic fatigue and degeneration of the shaft-paddle assemblies. A simplified, slow-speed, direct drive agitator, previously described in HW-52755, proved to be quite durable and satisfactory during extende… more
Date: December 24, 1959
Creator: Dunn, J. & Sloat, R. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary Report on the Use of Activated Carbon as a Catalyst for the Dissolved Oxygen-Aqueous Hydrazine Reaction

Description: Theoretically aqueous hydrazine will react with dissolved oxygen for form only nitrogen and water. Most of the experimental evidence, however, indicates that the reaction proceeds rather slowly in low-temperature systems. Tests are currently being conducted to determine whether or not it is feasible to use activated carbon to catalyze the reaction in filtered water. A system of this type would be useful in high temperature reactors when it becomes necessary to convert to single-pass operation.
Date: February 24, 1960
Creator: Demmit, T. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nuclearly Safe Mass Limits, Volume Limits, Infinite Cylinder Diameters and Slab Thicknesses for Slightly Enriched Uranium Rods in Light Water

Description: Graphs have been made which show the nuclearly safe parameters for uranium rods in light water with uranium enrichments up to five weight percent U-235. These data were to serve as a guide to those persons who may be involved with the maintenance of nuclear safety in handling and processing operations with slightly enriched uranium fuel elements. The data are applicable to fuel element fabrication and processing operations, and in general to those operations involving the handling and storage o… more
Date: May 24, 1960
Creator: Clayton, E.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Termination Report for Development Test IP-306-K Spline Coilers at K Reactor

Description: A reliable spline disposal system is necessary for full utilization of the Poison Spline Control System. The spline choppers were not reliable enough so a spline coiler was developed and designed to replace the choppers. A Development Test, IP-306-X (HW-63820), was issued authorizing on-pile testing of the spline coiler at X area. This report closes the Development Test and discusses the use of spline coilers.
Date: June 24, 1960
Creator: McCarthy, P. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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