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Scratch Depth Measurement Methods

Description: Judging scratch depth or surface roughness by unaided visual inspection under controlled conditions, while rapid and popular, is not quantitative. Comparison methods improve reproducibility but are generally not applicable to evaluation of depths of single widely spaced scratches. Stylus-type contour recorders yield valuable scratch contour data but may themselves plow through soft materials and fine details. Depth measuring microscopes are particularly applicable to measurement of pinhole dept… more
Date: February 26, 1959
Creator: Brenden, B.B.
Partner: UNT Libraries Government Documents Department
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Chemical Reactivity of Uranium Monocarbide and Uranium Mononitride with Water at 100°C.

Description: The monocarbide and the mononitride of uranium are potentially useful ceramic nuclear fuel materials. This paper reports the results of exploratory investigations of the reactions of uranium monocarbide and uranium mononitride with boiling water. Uranium dioxide, chemically stable in deoxygenated boiling water, was used as a control.
Date: February 26, 1959
Creator: Newkirk, H. W.
Partner: UNT Libraries Government Documents Department
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Detailed Procedure for K Reactors Rear ace Decontamination by Chemical Flush or the Rear Crossheaders, Pigtails and Nozzles as Authorized by the Production Test Authorization IP-239-N.

Description: The purpose of this procedure is to present a detailed, chronological presentation of the preliminary decontamination and post decontamination steps necessary to fulfill the requirements of the Production Test Authorization IP-239-N. The procedure attempts to present the required operation in sufficient detail to successfully accomplish the intent of the test. Certain procedures involve operations of a standard nature and have not been elaborated upon to any great extent, as it is expected tha… more
Date: February 25, 1959
Creator: Crossman, W.A.
Partner: UNT Libraries Government Documents Department
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Random Loading of E-Metal Dissolver

Description: Nuclear safety in the dissolution of irradiated 0.95 U235 enriched fuel has been investigated. In particular, critical conditions of fuel of this enrichment in a 52-inch diameter dissolver crib were studied. Since a crib this size is not safe by geometry, dissolution procedures as well as maximum safe batch sizes were analyzed. Uranium-water lattices are normally studied in systems in which rods are uniformly dispersed in the moderator. The results of such a study for 1.34-inch diameter solid … more
Date: February 25, 1959
Creator: Ketzlach, M.
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.
Partner: UNT Libraries Government Documents Department
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The Use of Tetravalent Uranium and Hydrazine as Partitioning Agents in Solvent Extraction Process for Plutonium and Uranium

Description: In solvent extraction purification processes such as are used at Hanford, the fuel elements or "slugs" from the reactor containing uranium, plutonium, and fission products are dissolved in nitric acid, adjusted to the required feed composition, and pumped to the solvent extraction columns. Figure 1 in a schematic diagram of such a solvent extraction process. In the A column, the uranium and the plutonium are extracted into an organic phase while the bulk of the fission products remain in the aq… more
Date: February 1, 1959
Creator: Buckingham, J.S.; Colvin, C.A. & Goodall, C.A.
Partner: UNT Libraries Government Documents Department
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Concentration and Final Purification of Neptunium by Anion Exchange

Description: It is anticipated that neptunium will be recovered in the Purex process by solvent extraction or ion exchange methods as a nitric acid solution of greater than 0.1 g. Np/1 and containing varying amounts of fission products, plutonium, uranium, and thorium, including Th234 (UX1). At the present time this solution is thermally concentrated in the Purex L-cell package to several grams of neptunium per liter. In this operation the solution is contaminated rather badly with plutonium and stainless s… more
Date: February 10, 1959
Creator: Ryan, J.L.
Partner: UNT Libraries Government Documents Department
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The Nuclear Safety of Fissile Materials

Description: Whenever fissile materials are handled in significant quantities such as in fuel element fabrication, separation processes, or in exponential and/or critical experiments a potential criticality hazard exists. The usual procedure which is followed by those persons conducting critical mass experiments is to either place the potential reactor in a heavily shielded cell or to conduct the experiments remotely in which case distance provides a measure of safety in the event of an unscheduled radiatio… more
Date: 1959-02-11?
Creator: Clayton, E.D.
Partner: UNT Libraries Government Documents Department
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Flow Decay After an Electrical Power Outage in the PRTR

Description: Previously, W. S. Figg and T. W. Ambrose (HW-51767 Rev) have investigated the problem of flow decay following electrical power loss to the PRTR primary coolant pumps. However, since the time of their study many reactor piping changes have been made in the design; therefore, it has become advisable to re-examine the problem incorporating these changes.
Date: February 6, 1959
Creator: Muraoka, J.
Partner: UNT Libraries Government Documents Department
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Heat Transfer in Radiant- Heat Spray Calcination

Description: The fixation of aqueous radioactive wastes in a stable solid media by means of calcination has been the subject of considerable research and development effort. Several methods of doing this on a continuous basis have been devised and a few have been demonstrated to be feasible for the handling of non-radioactive or low activity simulated wastes. Currently an investigation of calcination by means of radiant-heat spray drying is being carried on by the Chemical Research Operation of the Hanford … more
Date: February 1, 1959
Creator: Johnson, B.M., Jr.
Partner: UNT Libraries Government Documents Department
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Bronze Furnace History 313 Building

Description: This study was started in May 1949 to find methods of reducing the number of element failures in the salt bath bronze furnaces. Determining the cause of the failure and methods of eliminating them is followed to completion.
Date: February 6, 1951
Creator: Correy, Thos. B.
Partner: UNT Libraries Government Documents Department
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Specifications for WAPD Loop

Description: Specifications for the proposed in-pile loop to be placed in the Hanford Reactor. The the purpose of the proposed installation of an irradiation facility accounting to a high pressure, high temperature recirculating loop for the Westinghouse Atomic Power Division (WAPD) is to test the integrity of fuel specimens. This report, in support of the feasibility study, cost estimates, and schedule, presents design specifications for the loop.
Date: February 16, 1955
Creator: Berberet, J. A.
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.
Partner: UNT Libraries Government Documents Department
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Automatic In-Line Monitor for pH, Gamma Activity and Uranium in the Metal Recovery Plant

Description: In connection with the development of in-line analytical equipment for monitoring pH, gamma activity and uranium concentration in process streams, experiments and tests were carried out during the past year and a half in the Metal recovery Plant on a pH monitor for the hydrogen ion concentration in neutralized waste, a continuous gamma activity monitor on the RCU, an automatic photometer for uranium in RAF, and an automatic polarograph for uranium in RAW. This letter is written to present up-to… more
Date: February 18, 1955
Creator: Reas, W. H.; Connally, R. E.; Koyama, K.; Michelson, C. E. & Van Meter, W. P.
Partner: UNT Libraries Government Documents Department
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Penetration of Respiratory Protective Equipment by Ruthenium at Building 202-S

Description: The four types of respirator cartridges used at the 202 S Building were tested against aerosols found at that location, and in the laboratory against non-radioactive gaseous ruthenium tetroxide. Positive penetration of two types of cartridges was shown with one process aerosol. Gaseous ruthenium tetroxide penetrated all types of cartridges tested. Leaks were found in some of the cartridges. Particle size of aerosol particles was measured by means of cascade impactor samples and electron photomi… more
Date: February 21, 1955
Creator: Gill, W. E.
Partner: UNT Libraries Government Documents Department
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Examination of Zirconium Exposed to 190 MWD/AT

Description: A production test composed of preformed zirconium samples was prepared by R. S. Kemper of the Physical Metallurgy Unit⁽¹⁾ to determine the effect of exposure time and the influence of prior mechanical cold work on changes occuring [sic.] during irradiation. The first section was delivered to Radiometallurgy Unit is April, 1954, for examination after an exposure of 190 MWD/AT.
Date: February 11, 1955
Creator: Kelly, W. S.
Partner: UNT Libraries Government Documents Department
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The Alpha Half-Life of the Isotope Pu-241

Description: A plutonium solution of known Pu-241 content was purified by solvent extraction techniques to remove uranium and americium impurities. Portions of this purified solution were then analyzed for U-237 as a function of time. Since the growth of U-237 occurs directly by the alpha decay of Pu-241, these measurements provided sufficient data for calculation of the Pu-241 alpha half-life, which was found to be 2.91 ± 0.50 x 10⁵ years.
Date: February 15, 1955
Creator: Gift, M. W.
Partner: UNT Libraries Government Documents Department
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Examination of Donut on Rupture Slug No. 14

Description: Pursuant to Dr. Kingdon's request for specific information concerning the donut pictured on pages 26-29 of WAPD-64, a close examination of this defect on Failure No. 14 was made. The slug was examined through 10 inches of Pb-glass and photographs were made. A clay impression of the surface area containing the donut was obtained, and using this impression, an Armstrong's Adhesive replica of this can wall surface area was cast.
Date: February 19, 1957
Creator: O'Keefe, D. P.
Partner: UNT Libraries Government Documents Department
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Elastic Analysis of Stress Conditions in a Reduction Bomb (Task III Replacement Pressure Vessel Model-1302)

Description: Several failures have occurred in reduction bombs used in metal production operations. A test program is being initiated to evaluate new metals for the construction of the bomb. In the test program, a tensile specimen is cycled through temperatures simulating operating temperatures, and the time to rupture is recorded in order to estimate the life in operation of a reduction bomb made with the candidate metal. In order to find the worst stress condition, the compressive, hoop, and bending st… more
Date: February 19, 1954
Creator: Merckx, K. R.
Partner: UNT Libraries Government Documents Department
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The Determination of Total Plutonium in the Presence of Aluminum

Description: Introduction: "The adoption of aluminum nitrate as salting agent in the Redox process made it imperative that a method be available for determining plutonium in the presence of aluminum. However, large amounts of aluminum have been found to interfere with the determination of plutonium by the lanthanum fluoride procedure. Previous attempts to increase the accuracy of the lanthanum fluoride method, by precipitating LaF3 from 4 M HF (rather than 2 M), have been successful only when the initial pl… more
Date: February 10, 1950
Creator: Burns, R. E. & Barton, G. B.
Partner: UNT Libraries Government Documents Department
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Chemical Research Section Progress Report for January 1950

Description: The following documents are progress reports that follow chemical research studies in subjects such as ruthenium tetroxile distillations, extraction-scrub studies of zirconium and niobium, and oxidation of plutonium and stabilization of plutonium(VI) during extraction of IAF solutions.
Date: February 15, 1950
Creator: Albaugh, F. W.
Partner: UNT Libraries Government Documents Department
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