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CHARGING AND DISCHARGING OF DEMINERALIZER RESINS. CORE I, SEED 2. Test Results (T-612085). Section 1

Description: An investigation was conducted to flush the 1BD coolant purification system demineralizer of resin and to measurc the radiation level at pornts on the resin discharge line. It was found that the system demineralizer was satisfactorily flushed of resin. It was also found that the amount removed is measured by the amount required to recharge the demineralizer. (J.R.D.)
Date: January 10, 1961
Partner: UNT Libraries Government Documents Department
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Diffusion of Krypton Through Uranium Carbide - Final Report

Description: This program was established to develop new information concerning the mechanism of diffusion of fission gases (krypton and xenon) through UO2 and UC. The work was to concentrated on measurements of diffusion rates in unirradiated materials in the temperature range of 1000°C to above 2000°C, these determinations being important to the projected use of refractory fuel materials in high-temperature, high-burnup reactors.
Date: January 10, 1961
Creator: Weinstock, J. J.; Pinkerton, A. P. & Ziegel, K. D.
Partner: UNT Libraries Government Documents Department
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NON-DESTRUCTIVE TESTING OF STAINLESS-CARBON STEEL WELDS. CORE I, SEED 2. Section 2. Test Results T-641300

Description: Results are presented which lead to the conclusion that all the welds that were radiographed appear to be satisfactory for continued use in the plant except in the 1A reactor coolant loop drain weld. The radiograph of this weld indicates the presence of a 3/8 in. transverse defect. The majority of the welds showed indications of porosity. (J.R.D.)
Date: January 10, 1961
Partner: UNT Libraries Government Documents Department
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Plutonium Release Incident at Oak Ridge National Laboratory

Description: A nonnuclear explosion involving an evaporator occurred in a shielded cell in the Radiochemical Processing Pilot plant at Oak Ridge National Laboratory. Plutonium released from the processing cell contaminated areas in the pilot plant building and nearby streets and building surfaces. The explosion is considered the result of rapid reaction of nitrated organic compounds formed by the inadvertent nitration of about 14 liters of a proprietary decontaminating reagent.
Date: January 10, 1961
Creator: King, L. J. & Bresee. J. C.
Partner: UNT Libraries Government Documents Department
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Proposal for charging heat treatment test elements GEH-10-44 & 45

Description: The objective of this irradiation is to determine the differences in irradiation behavior; typified by dimensional changes, surface roughness, and overall distortion; resulting from elements of similar fabrication history but different beta heat treating schedule. The fuel will be the inner tube only of an NPR fuel assembly. Both elements were heated in chloride salt at 730C; one was rapidly quenched and the other air cooled to obtain a wide variation in grain size and structure and residual st… more
Date: January 10, 1961
Creator: Kemper, R. S. & Young, F. E.
Partner: UNT Libraries Government Documents Department
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The Inhalation Toxicity of Indium Sesquioxide in the Rat

Description: Albino rats were exposed to a In/sub 2/O/sub 3/ dust aerosol of mean concentration 64 mg/m) for 3 months. The retention of In in the tissues and the mobilization of In from the lungs and tracheobronchlal lymph nodes were determined. The results indicate chemical toxicity. (D.L.C.)
Date: February 10, 1961
Creator: Leach, L. J.; Scott, J. K.; Armstrong, R. D.; Steadman, L. T. & Maynard, E. A.
Partner: UNT Libraries Government Documents Department
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E-N and blanket conversions from analysis of tubes irradiated at H

Description: A block-loading of striped columns and tubes simulating a blanket loading were analyzed for product (Pu, tritium, E-metal) after irradiation in IP-255-A-9-FP. Results are rationalized to full-pile values; pile conversion ratios and pile gains are given.
Date: February 10, 1961
Creator: Lang, L. W. & Nechodom, W. S.
Partner: UNT Libraries Government Documents Department
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SOME EXPERIENCES IN THE WELD FABRICATION OF REFRACTORY METALS

Description: Discussion is given on the welding fabrication of tungsten, molybdenum, niobium, and tantalum. Properties which make the four refractory metals important are tabulatcd along with titanium which is given for comparison. Extensive evaluation was conducted using the gas, tungsten arc welding process employing both manual and machine welding. Design data were obtained exclusively from machine welded sheet materials. Flash welding, resistance spot welding and brazing, electron beam welding, and high… more
Date: February 10, 1961
Creator: Thompson, E.G.
Partner: UNT Libraries Government Documents Department
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Fission-Product Plateout From a Helium Gas Stream

Description: The experimental procedures used and the results obtained in studying the plateout of nongaseous fission products that may escape from a helium gas stream are discussed. Results show that significant quantities of high-activity fission products are volatilized from powdered uranium dioxide at 1800 deg F, and the gross activity for each of the materials (Nichrome, type 302 stainless steel, and quartz) exposed to the fission product vapors follows the same general pattern. Some indication is give… more
Date: March 10, 1961
Creator: Johnson, D. E.; Tobin, J. M. & Buchanan, J. D.
Partner: UNT Libraries Government Documents Department
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A Method of Determining the Intermediate Energy Neutron Dose

Description: The intermediate energy neutron flux existing outside the biological shielding of reactors has not been studied to any great extent previous to this time, because of the lack of an instrument capable of detecting neutrons in the intermediate energy range. The instrument used at the MTR utilizes polyethylene spheres of various sizes to give different amounts of moderation and absorption to the impinging neutrons. A procedure for the approximate determination of the relative number of intermediat… more
Date: March 10, 1961
Creator: Hankins, D. E.
Partner: UNT Libraries Government Documents Department
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Tensile Properties of Pyrolytic Graphite to 5000 F

Description: Tensile properties of pyrolytic graphite were measured parallel to the basal planes from room temperature to 5000 deg F. The gage section of the test specimen was 0.06 by 0.10 in. in cross section and3/4-in. long. The specimens were heated in a helium atmosphere by an external graphite heater and were tested at a strain rate of approx 2 x 10/sup -//sup 4/ in./in./sec. Tensile strengths at room temperatare varied from 6,000 to 19,000 psi with elongations of less thsn 1%. At 3000 deg F the streng… more
Date: March 10, 1961
Creator: Kotlensky, W. V. & Martens, H. E.
Partner: UNT Libraries Government Documents Department
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VARI-II

Description: Writing the VARI-II Program was motivated by the need for a method of analyzing the results for the Absorber Burn-Up Experiment in progress at the Vallecitos Atomic Laboratory.
Date: March 10, 1961
Creator: Russell, J. L. (John L.), Jr.
Partner: UNT Libraries Government Documents Department
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Critical Path Scheduling in Maintenance

Description: Summary: The following narrative interspersed with figures and attached reference exhibits is designed to acquaint the reader with the scheduling procedure developed at ORGDP, trial results and evaluation, subsequent improvement, further application, and use in conjunction with our IBM 7090 Computer.
Date: April 10, 1961
Creator: Gritzner, C. L.; Jones, J. P. & Ellis, J. M.
Partner: UNT Libraries Government Documents Department
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Examinations of Pump Impellers From Sodium and Fused Salt Pump Endurance Tests

Description: Examinations of three Inconel pump impellers were made to establish the extent of cavitation damage and degree of carburization sustained during pump endurance tests. The pumps, two of which circulated fluoride salt and one sodium, operated for the bulk of the test programs in the temperature range 1000 to 1250 deg F. Cavitation damage was manifested in each of the impellers by the formation of deep pits (in excess of 1/4-in.), the location of damaged areas varying with impeller geometry. Pit f… more
Date: April 10, 1961
Creator: DeVan, J. H.
Partner: UNT Libraries Government Documents Department
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THE SNAP II POWER CONVERSION SYSTEM TOPICAL REPORT NO. 14. MERCURY MATERIALS EVALUATION AND SELECTION

Description: SNAP II is the designation for a 3 kw nuclear auxiliary power unit to be used in a satellite vehicle. The SNAP II System consists of a reactor heat source, a boiler, a Hg Rankine engine, an alternator, and a condenser. The corrosion and subsequent mass transfer resulting from the use of Hg as the thermodynamic wo:king fluid are important considerations in the selection of materials for the SNAP II System. Consequently, corrosion and mass transfer behavior were under study for the past three yea… more
Date: April 10, 1961
Creator: Nejedlik, James F.
Partner: UNT Libraries Government Documents Department
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Supplement A to PT-IP-183-A-98-FP: Evaluation of projection fuel elements for use in K process tubes

Description: The objective of this supplement is to authorize charging of ten tubes of ``bumper`` fuel elements and controls into each K Reactor. The test is designed to reevaluate the reduction in hot-spot incidence associated with fuel alignment within K Reactor ribbed process tubes for both natural and enriched uranium I&E fuel elements of the KIV geometry.
Date: April 10, 1961
Creator: Clinton, M. A.
Partner: UNT Libraries Government Documents Department
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Experiments On Alfven-Wave Propagation

Description: This paper reports an extension of previous experimental work with Alfven waves. We consider hydromagnetic waves propagating in a cylindrical plasma in a uniform axial magnetic field. The copper tube is filled with highly ionized plasma by an electrically driven switch-on ionizing wave. After the tube is filled with plasma, a hydromagnetic wave is induced by a radial current flow from the small molybdenum electrode to the copper tube. The force produced by this radial current together with the … more
Date: May 10, 1961
Creator: Wilcox, John M.; DeSilva, Alan W. & Cooper, William S., III
Partner: UNT Libraries Government Documents Department
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THE RECOVERY OF FISSION PRODUCT RARE EARTH SULFATES FROM PUREX 1WW

Description: Cerium- and 144 promethium-147, accompanied by rare earths resulting from fission or decay can be removed from Purex 1WW in>90% yield as an insoluble, crystalline sodium-rare earth double sulfate. Precipitation is initiated by a one-to-three hour equilibration at 90 deg C and centrifugation at 90 deg C to take advantage of the lower solubility of the double sulfate salt at a higher temperature. The sulfate concentration should be one molar and the solution pH at the time of precipitation should… more
Date: May 10, 1961
Creator: Wheelwright, E. J. & Swift, W. H.
Partner: UNT Libraries Government Documents Department
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The Recovery of Fission Product Rare Earth Sulfates from Purex LWW

Description: A research and development program aimed at devising processes for the economical recovery of the potentially valuable long-lived fission products from Purex waste has been under wat at Hanford for several years. When this work has begun, the concentrated waste was primarily a nitric acid solution (6 to 10 M HNO3) containing the fission products and relatively small concentrations of iron, sulfate, and other corrosion products. Flowsheets based on classical separation schemes and rather similar… more
Date: May 10, 1961
Creator: Wheelwright, E. J. & Swift, W. H.
Partner: UNT Libraries Government Documents Department
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Final report on production test IP-289-I, Supplement 1, H reactor export flow test

Description: The raw water export system forms the last ditch water supply system to the ``O`` and ``C`` type reactors; in the event of electrical and steam power failure, the export system is designed to supply enough raw water coolant. After the original export orifice was modified twice, the export system was retested.
Date: July 10, 1961
Creator: Cremer, B. R.
Partner: UNT Libraries Government Documents Department
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