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Air Lift Performance at Low Liquid Rates Using Oversized Piping and Lateral Runs

Description: The use of oversized piping in an air lift for transferring solutions at rates less than 5 liters per hour was proven feasible with certain limitations. Reliable operation was also obtained with air lifts containing a lateral run inserted between the point of air injection and the final discharge point. Discharge of the air lifts, especially at low liquid flows, was very erratic under the conditions studied. (auth)
Date: October 10, 1961
Creator: Chamberlain, H. V.
Partner: UNT Libraries Government Documents Department
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Catastrophic Oxidation of High-Temperature Alloys

Description: The growth of nonprotective, crust-like oxide films was encountered in high-temperature alloy systems that contain molybdenum, vanadium, or tungsten as strengthening additions. The cause of accelerated oxidation in such alloys appears to be associated with the characteristically low melting temperatures of oxides of these refractory elements. The factors that contribute to a breakdown of oxidation protection in these systems are outlined and remedial methods which may be used to avoid catastrop… more
Date: November 10, 1961
Creator: DeVan, J. H.
Partner: UNT Libraries Government Documents Department
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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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Chemical Processing Technology Quarterly Progress Report, April-June 1961

Description: The Idaho Chemical Processing Plant did not operate on fuel recovery during this period, due to extensive renovation and modiflcation of facilities. Potasslum fluoride was found to be an undesirable additive to the barium precipitating agent used in formation of barium fluozirconate, because of precipitation and loss of uranium, although essentially complete precipitation of zirconium was achieved. Addition of hydrofluoric acid with barium precipitant, to achieve a fluoride/zirconium mole ratio… more
Date: November 10, 1961
Creator: Bower, J. R.
Partner: UNT Libraries Government Documents Department
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CHEMISTRY DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING JUNE 20, 1961

Description: Progress in the fields of nuclear chemistry, isolation and chemical properties of synthetic elements, chemical separation of isotopes, radiation chemistry, organic chemistry, chemistry of aquecus systems, electrochemistry of corrosion, nonaqueous systems at high temperature, and chemical physics for the year ending June 20, 1961, is reported. Separate abstracts were prepared for each topic. (M.C.G.)
Date: October 10, 1961
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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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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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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Fuel Cycle Program. A Boiling Water Reactor Research and Development Program. Quarterly Report No. 5, July 1961-September 1961

Description: Advanced Fuel Power-Limit Test. Fabrication of the 50 basic fuel assemblies has been completed. The three instrumented fuel assemblies were assembled and calibrated. Equipment and procedures have been prepared for the VBWR stability tests. Forty-two assemblies were irradiated during the last VBWR run. Average exposure for all assemblies which have been irradiated are tabulated. Detailed examination of the centermelt calibration assembly is in progress. Preliminary metallography indicates that c… more
Date: October 10, 1961
Creator: Hodde, J. A.
Partner: UNT Libraries Government Documents Department
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Hanford Studies for EGCR Combustion Characteristics. Summary Report

Description: The temperature, geometry, and flow conditions which exist in the EGCR were duplicated in a mock-up designated as the EGCR Burning Rig to establish the combustion conditions in the reactor. The conditions under which the EGCR Burning Rig will ignite were established and an analytical model was developed which predicts these conditions. Because the Burning Rig cannot exactly dupIicate the reactor situation the final prediction of the safety of the EGCR must rest on computer calculations employin… more
Date: October 10, 1961
Creator: de Halas, D. R.; Dahl, R. E. & Jackson, J. L.
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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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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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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Neptunium-237 content of E-metal

Description: An analytical program was carried out to obtain an accurate single point measurement of neptunium-37 content versus exposure for E-metal. Two large volume dissolver solution samples representing E-metal from the KW, KE, C, and DR reactors were obtained from the Redox Plant for the basis of analysis. The neptunium-237/U ratio was determined by direct analysis, and the exposure was estimated from the measured Pu/U ratio and the uranium-235 burn-out.
Date: October 10, 1961
Creator: Schneider, R. A.
Partner: UNT Libraries Government Documents Department
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NEUTRON FLUX AND Cd RATIO MEASUREMENTS IN THE HN-1 BEAM HOLE FOR THREE FUEL LOADINGS OF THE OAK RIDGE RESEARCH REACTOR

Description: Neutron flux measurements were made in the Oak Ridge Research Reactor beam hole HN-l shield plug. at low reactor power (N/sub L/) with three fuel configurations. The purpose of these tests was to determine the most favorable fuel arrangement in the region of the experimental hole in order to permit minimization of exposure time of an in-pile slurry loop experiment using pure thoria. It was found that the perturbed thermal neutron flux decreased by factors of 2, each 1.4 in., at the forward end … more
Date: October 10, 1961
Creator: Shor, A.J.f Mauney, T.H.
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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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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PT-IP-344-A-FP, Evaluation of Al-Si bond characteristics

Description: Tests in which aluminum-jacketed, Al-Si bonded uranium fuel elements were baked at various temperatures have shown there is a time-temperature relationship for Al-Si layer decomposition. For heat transfer and secondary coolant barrier considerations, the extent of bonding layer deterioration during fuel element irradiation is important. Currently, Al-Si bonded fuel elements show evidence of spire bond separation, and to a lesser degree, can-bond separation following irradiation. Such evidence h… more
Date: November 10, 1961
Creator: Clinton, M. A.
Partner: UNT Libraries Government Documents Department
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D-Reactor Graphite Burnout Interim Report: IP-25A(PT-105-532-E)

Description: The oxidation rate of the moderator in D-Reactor has been monitored from samples placed along the length of process tube channel 3478. During the interval from August 8, 1960, to August 10, 1961 were very high, up to 40%/KOD (1000 operating days). From the shape of the front-to-rear burnout profile, the oxidant appears to be oxygen and/or water.
Date: November 10, 1961
Creator: Ryan, B. A.
Partner: UNT Libraries Government Documents Department
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