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Army Gas Cooled Systems Program Engineering Core Test

Description: This report describes an experimental test that was initiated to supplement the design of the GCRE-1 core, and presents the results that were obtained.
Date: January 30, 1959
Creator: Blakley, J. W.
Partner: UNT Libraries Government Documents Department
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DETERMINATION OF MAXIMUM PERMISSIBLE LEAKAGE FROM THE HRT PROCESS STEAM SYSTEM

Description: Calculations were made to determine the radiation hazard to HRT personnel as a result of leakage to the atmosphere from the process steam system in the event of a heat exchanger tube rupture. These calculations show that with the present four-minute delay before dumping approximately 1020 lb of fuel solution may be transferred to the steam system. The radiation hazard from fission products in the atomosphere will be negligble if the steam killer blower is operating. If this blower is not operat… more
Date: January 30, 1959
Creator: Gift, E.H.
Partner: UNT Libraries Government Documents Department
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Dissolution of Zirconium Matrix Fuels in Molten Fluoride Salts

Description: The application of the Volatility Process for reprocessing spent reactor fuels to zirconium fuel elements requires the conversion of the fuel to a fluoride form. This conversion can be accomplished by the dissolution of such fuels in a bath of molten fluoride salts with a hydrogen fluoride sparge. Studies with dummy zirconium fuel elements showed dissolution rates averaging 2 mg/sq cm-min. The effect of submergence, geometrical configuration, and HF impingement rate appeared more significant th… more
Date: January 30, 1959
Creator: Horton, R. W. & Whatley, M. E.
Partner: UNT Libraries Government Documents Department
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Quarterly Report of the Solution Materials Section for the Period Ending January 31, 1959

Description: Deposition of U, Cu, and Ni sulfates from dilute simulated HR fuel solution circulated through a heated Zircaloy-2 pipe section is reported. It was found that deposition occurred under boiling conditions in horizontal pipes because of a gas space which prevented wetting in the upper part of the pipe. Other salt deposition studies in an in-pile loop are reported. Effectiveness of oftwo different hydroclone mountings in removing corrosion products from a loop was studied. Results of chemical stab… more
Date: January 30, 1959
Creator: Griess, J. C.; Savage, H. C.; Greeley, R. S.; English, J. L.; Bolt, S. E.; Hess, D. N. et al.
Partner: UNT Libraries Government Documents Department
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Solid State Division Quarterly Progress Report: August 1952

Description: This quarterly progress report discusses the ongoing work within the Solid State Division at the Oak Ridge National Laboratory for the period ending August 10, 1952. Projects discussed include radiation metallurgy, engineering properties, fused salts, crystal physics, and solid state reactions.
Date: January 30, 1959
Creator: Billington, D. S. (Douglas S.) & Howe, J. T.
Partner: UNT Libraries Government Documents Department
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1706 KE Water Treatment for Out-of-Reactor Test Facilities.

Description: Water treatment systems for preparing and maintaining high purity water in out-of-reactor or in-reactor test oops are becoming increasingly important. In out0of-reactor experiments the presence of ionic impurities in the water has a marked influence on film formation and corrosion rates. It is therefore , imperative that these impurities be maintained at the lower practical concentration.
Date: March 30, 1959
Creator: Demmitt, Thomas F.
Partner: UNT Libraries Government Documents Department
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Hazards and Safety Measures Related to Nuclear-Powered Merchant Ships: An Annotated Bibliography of Declassified Literature

Description: This compilation contains 202 abstracts of reports and documents on subjects related to maritime reactor safety; the abstracts are indexed in thc AEC Abstracts of Classified Reports'' (ACR). These ACR references were listed as unclassified or declassified in TID-4021, TID-40.35, and TID-4035, Supplement 1. The abstracts were selected as a part of the preparation of the classified bibliography (ALI-50, printed August 30, 1958) on this same subject. (See also SO-6200, Septcmber 15, 1957, unclassi… more
Date: March 30, 1959
Creator: White, M. K.
Partner: UNT Libraries Government Documents Department
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Protection of Stainless Steel Sheathed Thermocouples from Uranium at 500 C

Description: Ceramic insulated, stainless steel sheathed thermocouples have been used to monitor temperatures of encapsulated uranium specimens, both in-reactor and out-of-reactor. No operational difficulties are encountered at low temperatures, but at a temperature of 700 C or greater, a eutectic is formed between uranium and iron. This reaction destroys protective sheath and results in thermocouple failure. A typical example of the phenomenon has been reported by J.W. Geffard of the Fuels Development Oper… more
Date: March 30, 1959
Creator: Sake, J.H.
Partner: UNT Libraries Government Documents Department
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PRTR Fuel Element Nuclear Safety

Description: A study of the nuclear safety in the storage and transportation of PRTR fuel elements has been made. This study was based on 7-rod clusters of plutonium-aluminum allow fuel elements containing 1.8 per cent Pu by weight. Each cluster is 7 feet 4 inches in length and contains 270 grams plutonium. Drawings of the "New Fuel Storage Pit" (H-3-11030) have been reviewed for nuclear safety. Nuclear safety criteria for the design of a lead shielded fuel transfer cask as well as criteria for the storage … more
Date: March 30, 1959
Creator: Ketzlach, N.
Partner: UNT Libraries Government Documents Department
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THE SELF-DIFFUSION OF NIOBIUM--III. Final Progress Report for July 1, 1958 to January 1, 1959

Description: The self-diffusion coefficient of niobium was measured over the temperature range 1535 to 2120 C, using the radioactive isotope Nb95 as the tracer. The data for the temperature dependence of the self-diffusion coefflcient are best fitted by the equation D = (12.4 cores consistin 0.2) exp STA(-105,000 cores consistin 3OOO)/RT! cm/sup 2//sec. (auth)
Date: March 30, 1959
Creator: Resnick, R.; Castleman, L.S. & Seigle, L.
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Unit Operations Section Monthly Progress Report for January 1959

Description: Two alternate systems, acetic acid-nickel and acetic acid-cobalt, were examined for possible replacement of the corrosion system: ferric chloride-nickel which is being used in the current transpiration corrosion protection studies. Two Fluorox fluidized bed runs were made, of 9 and 58 hr duration, in which dry air and oxygen were used as oxidizing and fluidizing gases. Tests of the hydroclone classification of thoria indicated that more than 95% of the +0.5 micron particles can be removed from … more
Date: April 30, 1959
Creator: Bresee, J. C.; Haas, P. A.; Horton, R. W.; Watson, C. D. & Whatley, M. E.
Partner: UNT Libraries Government Documents Department
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CUREBO: A GENERALIZED TWO-SPACE-DIMENSIONAL CODING WITH CROSS-SECTION AND DEPLETION CALCULATIONS FOR THE IBM 704

Description: The CUREBO code for the IBM 704 is described. The code is divided into three parts including the calculation of nuclear cross section of the various physical components of a reactor (WOX7), the solution of the multigroup diffusion equations in two-space dimensions in order to find neutron fluxes and sources for an operating reactor containing these components ( CURE), and the calculation of fuel and poison depletion as a result of operating this reactor under steady- state conditions (BO2). (au… more
Date: April 30, 1959
Creator: Archibald, J.A. Jr.
Partner: UNT Libraries Government Documents Department
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Description of Purex Plant Process

Description: A brief summary, with reference literature for details, of pertinent and important process flowsheet conditions which are in use in the Purex Process is presented. (auth)
Date: April 30, 1959
Creator: Irish, E. R.
Partner: UNT Libraries Government Documents Department
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Preliminary Studies of Scavenging Systems Related to Radioactive Fallout. Summary Report

Description: Preliminary studies were made of the relationship between the size of particles suspended in the lower atmosphere and the amount and nature of radionuclides they contain. Emphasis was placed on the distribution of strontium90. From a limited number of analyses, it was found that strontium-90 is associated primarily with particles below 0.1 micron in diameter. Preliminary studies were made of scavenging of particles by liquid water droplets. Studies are included of sticking probability and the e… more
Date: April 30, 1959
Creator: Rosinski, J. & Stockham, J.
Partner: UNT Libraries Government Documents Department
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Preliminary Studies of Scavenging Systems Related to Radioactive Fallout : Summary Report, April 1, 1958 to March 31, 1959

Description: This report is the final in a series of preliminary reports that follow the studies of scavenging systems related to radioactive fallout. The project consisted of two phases: preliminary experiments to relate the sizes of particles in air to specific radioisotopes, and preliminary laboratory studies of scavenging of particles by liquid drops, including studies of sticking probability and effects of Brownian motion and water vapor diffusion.
Date: April 30, 1959
Creator: Rosinski, John & Stockham, John D.
Partner: UNT Libraries Government Documents Department
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Production Test IP-261-C determination of power rate meter response

Description: This test will determine approximately the relationship between the power rate of rise indicated by the power rate meter and the actual pile power, rising period, and power rate. The actual pile power and power rate cannot be measured accurately during rapidly changing conditions; it is the intent of this test primarily to demonstrate that rate of rise protection offered by the power rate meter an be calculated to the same order of accuracy as the measurements of actual conditions.
Date: April 30, 1959
Creator: Simpson, D. E.
Partner: UNT Libraries Government Documents Department
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Quarterly Report of the Solution Materials Section for the Period Ending April 30, 1959

Description: Studies concerned with the deposition of salts from simulated fuel solution under boiling conditions were continued. Additional deposition tests were carried out in loop L-2-23 in which the core section was heated. Several reagents were tested to determine their ability to dissolve stainless steel corrosion products. A simulated HRT fuel solution was stable with regard to U concentration when diluted to 23 ppm at 250 C; however, some Cu was lost from solution. Preliminary tests in a uranyl sulf… more
Date: April 30, 1959
Creator: Griess, J. C.; Savage, H. C.; Greeley, R. S.; English, J. L.; Bolt, S. E.; Hess, D. N. et al.
Partner: UNT Libraries Government Documents Department
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Results of reverse flow experimental tests for C operational charge-discharge tube at low tub powers

Description: The purpose of this report is to present the results of laboratory experiments in which coolant water flowed backwards through a ``C`` reactor process tube with operational charge-discharge front fittings under conditions of typical reactor rear header pressures and post-scram rear header water temperature and tube powers. This information is of value in planning and interpreting transient experiments investigating the consequences of the rupture of reactor front face piping to a single tube.
Date: April 30, 1959
Creator: Fitzsimmons, D. E. & Hesson, G. M.
Partner: UNT Libraries Government Documents Department
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Studies of Zirconium-Iron-Tin Alloys. Report No. 6 (Final) for July 1, 1958-March 31, 1959

Description: The intermetallic compounds of the zirconium-irontin system (i.e., ZrFe/ sub 2/ and Zr/sub 4/Sn) were studied at 500 and 1100 C. The alloys were prepared from iodide zirconium and high-purity iron and tin by nonconsumableelectrode arc melting techniques under an inert atmospherc. Specimens were encapsulated in Vycor and annealed at the prescribed temperatures followed by a water quench. Data were gathered through the use of metallographic, x-ray diffraction, visible incipient melting, and magne… more
Date: April 30, 1959
Creator: Tanner, L.E. & Simcoe, C.R.
Partner: UNT Libraries Government Documents Department
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Equilibrium Extraction Characteristics of Alkyl Amines and Nuclear Fuels Metals

Description: In the period March 31 to June 31, 1959 work has progressed on zirconium, molybdenum, and samarium and has been initiated on ruthenium. For the first three metals, studies have been made on the following variables; amine concentration in the organic phase, metal concentration in the aqueous phase, nitric acid concentration in the aqueous phase, effect of an added nitrate on the extractions carried out in 2N HNO3, diluent type, and amine type and branching amine, secondary amine, and primary.
Date: June 30, 1959
Creator: Mason, Edward A. & Vaughen, Victor C.
Partner: UNT Libraries Government Documents Department
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FUNDAMENTALS OF DIFFUSIONAL BONDING--IV. Fourth Annual Progress Report for July 1, 1958 through June 30, 1959

Description: Investigatlon of interdiffusion in the aluminumuranium system and of the effects of applied pressure on such systems was about completed. The growth kinetics of the UAl/sub 3/ phase were determined at 400 to 600 C and at pressures of 1 1/4, 5, and 10 tsi. The origin of the macroscopic defects occurring in the UAl/sub 3/ layer during interdiffusion was clarified. The solubility range of UAl/sub 3/ was determined by a nuclear track emulsion technique to be about 2.6 at.% uranium. Exploratory runs… more
Date: June 30, 1959
Creator: Castleman, L.S. & Seigle, L.
Partner: UNT Libraries Government Documents Department
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Heat Transfer in Septafoil Geometries by Mass-Transfer Measurements

Description: In conjunction with Gas-Cooled Reactor heat-transfer studies, local and mean heat-transfer factors are predicted from the heat transfer-mass transfer analogy using subliming naphthalene in air. Experimentation was conducted on 1-in.-dis septafoil rods in a 4-in. -dis flow channel with rod center-to center spacings of 1.10, 1.25, and 1.40 in. at a Reynolds modulus of approximately 60,000. Ratios of local mass transfer to mean mass transfer for a given rod vary as much as from 0.7 to 1.3 (outer r… more
Date: June 30, 1959
Creator: Wantland, J. L. & Miller, R. L.
Partner: UNT Libraries Government Documents Department
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