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Irradiation of U-Mg Matrix Fuel Materials to High Exposures

Description: An experiment designed to evaluate the in-pile performance of the U-Mg fuel material when irradiated to high burnups has been completed. Twelve specimens of the fuel material which contained uranium particles that packed 50 volume per cent, (91.5 weight per cent), uranium in a magnesium matrix were canned in Zircaloy cans and irradiated in the Materials Testing Reactor to 0.1 (1000 MWD/T), 0.3 (5000 MWD/T), 1.0 (10000 MWD/T) and 2.0 20000 MWD/T) per cent burnup of the total uranium atoms; more … more
Date: August 1, 1956
Creator: Freshley, M. D. & Last, G. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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NO₂ Exposures from Operations in the 224 U Building

Description: As recommended in a previous report a study of the NO₂ and HNO₃ exposures of plant personnel in the 224 U Building has been made. Concentrations of NO₂ and HNO₃ from the 224 U roof stack, in the concentrator cells, and in the calcining pot rooms have been determined. The problems have been outlined and recommendations have been made for its alleviation.
Date: May 15, 1956
Creator: Gill, W. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Examination of Irradiated Uranium-Chromium Alloy Slugs

Description: Production Test 313-105-13-M authorized the irradiation of a uranium - 0.4 atomic per cent chromium alloy to determine the relative stability of this material during irradiation. Five tubes, each containing six four-inch alloy slugs, were irradiated to exposures ranging from 156 to 834 MWD/T. This report describes the results of the visual examination of the bare uranium alloy slugs and the results of the test to determine slug breaking strength. The breaking strength of both the U-Cr alloy slu… more
Date: February 14, 1955
Creator: Kratzer, W. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of Biological Hazards from Ruthenium Particulates: I. Studies of Percutaneous Absorption, Gastrointestinal Absorption, and Gastrointestinal Holdup

Description: Studies are described of the percutaneous absorption and gastrointestinal absorption in the rat of ruthenium administered in the form of "insoluble particulates." Results are also reported on the gastrointestinal holdup of these particulates.
Date: March 1, 1956
Creator: Thompson, R. C.; Hollis, O. L. & Oakley, W. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radiological Sciences Department Quarterly Progress Report Research and Development Activities October-December, 1955

Description: This twenty-fifth quarterly report of the research and development activities of the Radiological Sciences Department, Hanford Atomic Products operation, as before, includes some items charged to control but included for general interest. The previous report of this series was numbered: HW-39624, October 11, 1955. Progress is reported in the following studies: a radiobiological-ecological survey of the Columbia River; the toxic effects of continuous low-level exposure to I¹³¹ in pigs; Pu metabo… more
Date: January 11, 1956
Creator: Parker, H. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Comparative Study of Hanford and Utah Range Sheep

Description: Observations on sheep representing flocks in Utah adjacent to the Nevada Proving Ground were compared with findings made on experimental sheep exposed to various amounts of radioiodine. The Utah sheep showed no evidence of the radiation damage observed in experimentally treated sheep. Estimations of amounts of radioiodine on vegetation required to cause serious thyroid damage following a contamination event are included.
Date: November 30, 1953
Creator: Bustad, Leo K.; Marks, S.; Dockum, N. L.; Kalkwarf, D. R. & Korrberg, H. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radiometallurgical Hardness and Weight Results on Irradiated Zirconium and Zircaloy-2 Samples as Requested by the Pile Development Unit

Description: Eight zirconium and eight Zircaloy-2 process tube samples were irradiated in the "H" test loop, Tube 0961-H, so that the corrosion tendencies of the material might be evaluated when exposed to radiation. The samples were delivered to the Radio-metallurgy Building in January, 1955, and examined as requested by C. D. Wilson of the Pile Development Unit, Pile Technology Section.
Date: April 28, 1955
Creator: Kelly, W. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Final Report Production Test 105-585-A Functional Testing of Teflon Flexible Connector, 105-C Type

Description: A new type of flexible hose connector consisting of a Teflon tube enclosed in a stainless steel wire braid sheath was proposed for use on 105-C rear face in late 1954. A test was initiated to determine the suitability of Teflon, and specifically Fluoroflex Teflon compound for rear face application. Probable useful life limit is estimated at 10⁶ R, which would be attained in about three years in contact with fresh effluent.
Date: July 15, 1955
Creator: Cooke, J. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Surface Structure of Pile Irradiated 2S Aluminum

Description: The surfaces of cold rolled, half hard, nitric acid treated, autoclave etched, 2S aluminum coupons were studied by optical and electronoscopic methods, before and after exposure to hot water alone and hot water and neutron bombardment. The non-exposed aluminum surfaces have a characteristic pattern which is absent in the exposed coupons. All of the exposed coupons were corroded. In general the coupons exposed to the higher flux intensities of irradiation were more severely corroded than those e… more
Date: August 1, 1955
Creator: Borasky, R. & Mastel, B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Thermal Annealing Kinetics of C₀ Spacing Damage in Irradiated Graphite

Description: Graphite suffers radiation damage when exposed to high energy particles. Many of its physical and chemical properties are changed. One of the effects which is easily measured is an increase in the interlayer or C₀ distance of the crystal lattice. This has been attributed to the displacement of atoms or groups of atoms into interstitial positions of the lattice forcing the planes apart. The C₀ expansion may be annealed out by heating the damaged crystal to high temperatures. This paper deals wit… more
Date: June 20, 1955
Creator: Nightingale, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Thermal Annealing Kinetics of Interlayer Spacing Damage in Irradiated Graphite

Description: The primary objective of this work is to add to the understanding of irradiated graphite. This report describes an experimental technique whereby changes in crystal lattice parameter may be studied as a function of time at constant temperature. The results given here are limited to changes in the C₀ spacing for a typical sample of irradiated graphite in the temperature range 100 to 750 C.
Date: June 21, 1955
Creator: Nightingale, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Stability of Purex Solvent to Radiation and Chemical Attack

Description: The effects of variables on the rate of Purex solvent deterioration were investigated with the emphasis on those deterioration products which cannot be removed by carbonate washing. The deterioration rate was found to be directly proportional to the acid and nitrate ion concentrations, and proportional to the square root of the concentration of nitrite ion. Other observations on the effects of temperature, relative merits of brand name solvents, and the effects of radiation are included. A meth… more
Date: May 24, 1955
Creator: Swanson, J. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Temperature Calculations For UO₂ Fit Tolerance Experiment

Description: Prevailing dimensional tolerance for sintered UO₂ reactor fuel components to be enclosed in metal jackets are expensively small. For instance, the PWR fuel pellet, as of November, 1955, consisted of a centerless ground UO₂ cylinder 0.3560" (+0.0005", -0.000") in diameter and 0.3527" (±0.0008") long. This pellet was designed to fit in a Zircaloy tube 0.3585" (+0.0005", -0.0000") inside diameter. The use of UO₂ shapes as pressed, or extruded, and sintered with diameter variations controlled to a … more
Date: May 9, 1956
Creator: Roake, W. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Plasters and Elastomers in Radiation Fields: A Preliminary Evaluation

Description: With the construction of nuclear reactors, a great deal of emphasis has been placed upon studying the effects of radiation on the solid materials of construction. It has become necessary to consider radiation exposure as an environmental entity along with others so established such as temperature, electrical and mechanical stress, chemical resistance, weather, etc. Problems concerning the study of the behavior of materials that are thus increased when radiation exposure has to be evaluated sing… more
Date: May 4, 1956
Creator: Harrington, Robert.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Metallography of Irradiated Uranium

Description: Highly radioactive materials have to be examined behind massive shielding to protect personnel from the intense beta and gamma fields. Experience has shown that much maintenance time can be saved by mounting equipment to cell plugs so that a single machine can be removed without the necessity of shutting down the entire cell operation. Metallographic specimen preparation and photography have been reduced to an entirely remotized procedure. Various etchants have been tried and cathodic vacuum et… more
Date: March 30, 1956
Creator: Morgan, James R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Physics Research Quarterly Report: July, August, September 1955

Description: Under the general heading of Reactor Lattices are reported a new method of calculating resonance escape probabilities, results for the effective mass of a proton bound in the water molecule, and a comparison of similar techniques for calculating lattice constants developed independently by Hanford physicists and by a school of Russian physicists (as reported at the Geneva Conference). An estimate of maximum errors in f and η for thermal systems is described. Experiments and analysis thereof on … more
Date: December 7, 1955
Creator: Hanford Atomic Products Operation. Engineering Department. File Technology Section. Physics Research Sub-Section.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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