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Accumulation of Radioactivity in Columbia River Fish in the Vicinity of the Hanford Works

Description: Abstract: The data obtained from the radioassay of fish collected in vicinity of the Hanford Works between April, 1948 and June, 1950 are presented. Most of the radioactivity in the fish resulted from the concentration of p32 in the scales, bone, and certain visceral organs. The level of activity density in the fish was influenced by size, feeding habits and metabolic rate in addition to the activity density of the water. Changes in operation of nuclear reactors have resulted in progressive inc… more
Date: July 1, 1952
Creator: Olson, P. A., Jr. & Foster, Richard F.
Partner: UNT Libraries Government Documents Department
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An Aqua Recia Flowsheet for Uranium Dissolution

Description: Relatively long time cycles are required for the standard nitric acid dissolution of enriched uranium using safe batch size techniques for criticality control. Upwards of forty eight hours are required for the total dissolution of solid of I and E enriched slugs in nitric acid. The dissolution capacity may be increased by: (1) using a dissolver critically safe by virtue of its geometry or, (2)increasing the rate of uranium dissolution. Dilute agua regia -- a mixture of hydrochloric and nitric a… more
Date: July 21, 1959
Creator: Shefcik, J. J.
Partner: UNT Libraries Government Documents Department
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Coagulant Aids as Filter Aids

Description: The Hanford water treatment plants were operated for a number of years with alum as a coagulant and activated silica as a coagulant and a polyacrylamide as a filter conditioning agent. (other polyelectrolytes may be used.) Sufficient time has elapsed to make a comparison of the two methods of operation valid and useful. Such a comparison is the purpose of this paper.
Date: July 21, 1960
Creator: Conley, W. R.
Partner: UNT Libraries Government Documents Department
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Critical Tests for PRT Reactor

Description: This document authorizes the performance in accordance with the specifications noted, the PRTR Critical Tests described herein. The experiments described have the following objectives:
Date: July 1, 1960
Creator: Triplett, J. R.; Anderson, J. K.; Peterson, R. E.; Regimball, J. J.; Russell, J. T.; Schmid, L. C. et al.
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}}}
Partner: UNT Libraries Government Documents Department
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A Description of the Acetone-Dye Solution Method of Demarcating a Leak Process Tubing While in the Pile

Description: Abstract: "A method has been devised and successfully used for marking a leaking pile process tube prior to its removal from the pile, such that subsequent location of the leak is more easily accomplished. An acetone solution of Testor's Dark Red Airplane Dope is poured into the suspect tube. The solution leaks from the hole and stains the surrounding area a light pink. To date the method has been used on tubes 3573F, 0486F, 0867F, and 3670F."
Date: July 16, 1952
Creator: DeHollander, W. R.
Partner: UNT Libraries Government Documents Department
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Division of Reactor Development Programs Monthly Reports-June 1959

Description: Basic Studies. Sinterability experiments in the system UO2-PuO2 have continued, and data are available at one hour hold times across the UO2-PuO2 composition limits. Sintered densities appear to be markedly dependent on pressed densities with densification occurring very rapidly at higher pressing pressures. The following table illustrates the effect of one hour at temperature on final density for pure plutonium dioxide pressed to both 40 and 60 percent of theoretical density.
Date: July 15, 1959
Creator: Lewis, M.
Partner: UNT Libraries Government Documents Department
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Examination of Discharged Process Tubes

Description: Introduction: "The observations reported in this document were obtained by C.H. Pitt during his assignment to the Corrosion Group September through October 1951. The tubes examined were: 1.) 0893-F Discharged for corrosion examination after leaking; 2.) 1488-DR Discharged to determine caused of obstruction; 3.) 2276-D Discharged for corrosion examination; 4.) 2376-D Discharged for corrosion examination; 5.) 1185-H Discharged to evaluate the effect of magnesium front dummies."
Date: July 21, 1952
Creator: Dalrymple, R. S.
Partner: UNT Libraries Government Documents Department
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Fuel Core Tester - UT-2

Description: Report that "describes an instrument that nondestructively tests uranium fuel element cores by ultrasonic methods" (p. 2).
Date: July 18, 1960
Creator: Frederick, C. L. & Waldkoetter, G. L.
Partner: UNT Libraries Government Documents Department
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Graphite Sample Boring from Process Channels : Final Report, Production Test 105-389-P

Description: The following report records a total of forty-nine graphite core samples that have been bored from process tube blocks in the Hanford piles with the intention to provide results to indicate that core boring is an entirely practical operation over bore scraping in obtaining powder samples.
Date: July 10, 1951
Creator: Cole, J. B.
Partner: UNT Libraries Government Documents Department
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Hanford Controlled Potential Coulometer

Description: Report describing the Hanford Laboratory controlled potential coulometer. This includes the theory behind the coulometer, details of its circuitry, and performance tests. Appendix begins on page 23.
Date: July 11, 1960
Creator: Connally, R. E. & Scott, F. A.
Partner: UNT Libraries Government Documents Department
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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.
Partner: UNT Libraries Government Documents Department
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Hanford Neptunium Oxalate-Oxide Process Experience

Description: In recent months, relatively large quantities of neptunium-237 have been recovered from Hanford irradiated uranium. The over-all recovery process consisted of 1) isolation from Purex plant solutions by solvent extraction, to yield an impure neptunium nitrate solution contaminated principally with uranium, plutonium, and fission products (2) purification by anion exchange 3) precipitation of neptunium (IV) oxalate; and 4) calcination of the oxalate to yield neptunium (IV) oxide, NpO2. This paper… more
Date: July 1, 1959
Creator: Pollock, C. W. & Schneider, R. A.
Partner: UNT Libraries Government Documents Department
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Heat Transfer Testing

Description: Several tests are being performed and others being planned to investigate the role of heat transfer in corrosion processes. These tests are measuring both corrosion rates of metals (Zr-2 and X-8001 aluminum) under heat transfer, and the temperature rise associated with the buildup of the corrosion product. A brief description of these tests is given in this report.
Date: July 7, 1959
Creator: Doman, D. R.; Hokenson, J.F. & Lobsinger, R. J.
Partner: UNT Libraries Government Documents Department
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Integrated Radiological Instrumentation System Planning

Description: In recognition of the need for an integrated system plan for future development requirements for radiological instrumentation, this information report was written to provide the initial step concerning such a planning. The report is to be considered a basic information analysis of the present in-use plant radiological instrumentation, of the instrumentation now undergoing active development, and of the future development work contemplated.
Date: July 14, 1960
Creator: Spear, W. G.
Partner: UNT Libraries Government Documents Department
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Invention Report: Hermetically Sealed Closure on a Sheathed Thermocouple

Description: Applications of sheathed (metal) thermocouples may require in many instances, the insertion of the thermocouple thermal junction into an area that must be hermetically sealed to the outside. This same area usually contains highly reactive heat transfer medium such as an eutectic alloy of sodium and potassium of sodium alone. When fissionable materials are being irradiated, fission products that are driven off would also be present and must be contained under varying temperatures and pressures.
Date: July 12, 1960
Creator: Kosut, Bert S.
Partner: UNT Libraries Government Documents Department
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