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SINTERED ALUMINA AS A PUMP BEARING AND JOURNAL MATERIAL

Description: Design criteria and operating experience with the aluminum oxide bearing and journal combination as installed in canned rotor pumps in in-pile loops are described. No pump failures occurred in 8 pumps with A1/sub 2/0/sub 3/ bearings over a cumulative period of l0,000 hours due to wear or corrosion. Five failures due to slippage and/or electrical breakdown of the stator insulation are reported. (T.R.H.)
Date: November 26, 1957
Creator: Savage, H.C.
Partner: UNT Libraries Government Documents Department
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Pump Loops Used for Materials Testing in High Temperature Aqueous Solutions and Slurries

Description: Pump loops designed to operate at temperatures and pressures to 320 deg C and 2000 psia are described. The loops were used to circulate uranyl sulfate solutions and aqueous thoria slurries in out-of-pile tests for the aqueous homogeneous reactor program. As this phase of the aqueous homogeneous reactor program was completed, the loops were converted for use in studies of materials of interest to other types of reactors. Solutions or slurries are circulated in the loops by means of a 100-gpm can… more
Date: June 24, 1963
Creator: Savage, H.C.
Partner: UNT Libraries Government Documents Department
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Formation and use of oxide films to impede outgassing of metals

Description: From surface effects in controlled thermonuclear fusion devices and reactors meeting; Argorne, Illinois, USA (10 Jan 1974). Phenomena associated with the outgassing of metals are generally interpreted using models bascd either on desorption of compounds from the surface or on diffusion of dissolved gases from the interior of the metal. It is generally recognized that surface oxide films can serve to decrease outgassing rates of metals. However, the processes associnted with the outgassing of ox… more
Date: January 1, 1973
Creator: Strehlow, R.A. & Savage, H.C.
Partner: UNT Libraries Government Documents Department
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Effect of heat flux on the corrosion of aluminium by water. part 4 tests relative to the advanced test reactor and correlation with previous results.

Description: The corrosion of 8081 and X-8001 aluminum alloys and the resultant formation of an adherent corrosion product on the corroding surface were investigated under conditions (except radiation) comparable to those that will exist on the surface of fuel-element cladding during operation of the Advanced Test Reactor. Since previous experiments indicated that corrosion penetration of the aluminum clad was unlikely during a reactor cycle provided the water chemistry is properly controlled, most of the s… more
Date: February 1, 1964
Creator: Griess, J. C.; Savage, H. C. & English, J. L.
Partner: UNT Libraries Government Documents Department
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In-Pile Corrosion Test Loops for Aqueous Homogeneous Reactor Solutions

Description: An in-pile corrosion test loop is described which is used to study the effect of reactor radiation on the corrosion of materials of construction and the chemical stability of fuel solutions of interest to the Aqueous Homogeneous Reactor Program at ORNL. Aqueous solutions of uranyl sulfate are circulated in the loop by means of a 5-gpm canned-rotor pump, and the pump loop is designed for operation at temperatures to 300 ts C and pressures to 2000 psia while exposed to reactor radiation in beam-h… more
Date: December 21, 1960
Creator: Savage, H.C.; Jenks, G.H. & Bohlmann, E.G.
Partner: UNT Libraries Government Documents Department
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TOROID ROTATOR FOR SMALL-SCALE DYNAMIC CORROSION STUDIES-DESIGN, FABRICATION, AND OPERATION

Description: A description of the four-toroid rotator, a relatively simple apparatus particularly applicable to the determination of the corrosive effects of flowing solutions or slurries on structural materials, is presented in detail. In this apparatus flow of a liquid medium at known velocities is induced in a circular section of pipe without the use of pumps. Included are details of mechanical design, descriptions of equipment and instrumentation, a list of fabrication costs, and a discussion of operati… more
Date: November 15, 1956
Creator: Warner, R. M.; Moore, G. E. & Savage, H. C.
Partner: UNT Libraries Government Documents Department
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Effect of Heat Flux on the Corrosion of Aluminum by Water. Part Iii. Final Report on Tests Relative to the High-Flux Isotope Reactor

Description: The effect of very high heat fluxes on the corrosion of 1100 and 6061 aluminum alloys by water was investigated. The test conditions generally simulated those expected to exist during operation of the High-Flux lsotope Reactor. At heat fluxes between 1 and 2 x l0/sup 6/ Btu/hr-ft/sup 2/ and with coolant temperatures and velocities in the ranges of 13l to 250 deg F and 3l to 51 fps, respectively, a layer of boehmite ( alpha Al/sub 2/O/sub 3/- H/sub 2/0), which has low thermal conductivity, forme… more
Date: December 20, 1961
Creator: Griess, J. C.; Savage, H. C.; Rainwater, J. G.; Mauney, T. H. & English, J. L.
Partner: UNT Libraries Government Documents Department
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Tritium permeation through materials for steam generator systems

Description: Mixed isotope techniques and experimental apparatus have been developed for determining the rates of tritium permeation through metals at high temperatures. An inert gas or a controlled steam oxidizing atmosphere on the downstream side of the sample is used so that effects of surface oxidation and the formation of oxide coatings to impede tritium permeation can be determined. The validity of the method was demonstrated by determining the tritium permeability of nickel and comparing the tritium … more
Date: January 1, 1975
Creator: Bell, J.T.; Strehlow, R.A.; Redman, J.D.; Smith, F.J. & Savage, H.C.
Partner: UNT Libraries Government Documents Department
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In-Pile Loop Irradiation of Aqueous Thoria-Urania Slurry at Elevated Temperature. Design and in-Pile Operation of Loop L-2-27S

Description: An in-pile pump loop, designed to fit within horizontal beam hole HB-2 of the Low-Intensity Test Reactor (LlTR), was used to circulate an aqueous thoria- urania slurry while exposed to reactor irradiation. The total loop volume was about 1600 ml, including pump and pressurizer, but the slurry was confined to the 900-ml volume of the main loop stream by means of a sintered stainless steel filter. The filter was an important feature of the loop design in that it provided a thoria-free filtrate as… more
Date: February 14, 1962
Creator: Savage, H. C.; Compere, E. L.; Baker, J. M.; DeCarlo, V. A. & Shor, A. J.
Partner: UNT Libraries Government Documents Department
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Solvent extraction studies of coprocessing flowsheets: results from campaigns 3 and 4 of the Solvent-Extraction Test Facility (SETF)

Description: Experiments on tri-n-butyl phosphate solvent extraction of uranium and plutonium at full activity levels (Campaigns 3 and 4) were conducted in the Solvent Extraction Test Facility (SETF), located in one of the heavily shielded cells of the Transuranium Processing Plant. The primary objectives were: (1) to demonstrate and evaluate the first two cycles of the Hot Engineering Facility flowsheets (codecontamination and partial partitioning), and (2) to investigate and evaluate the use of HNO{sub 2}… more
Date: May 1, 1982
Creator: Collins, E. D.; Benker, D. E.; Bigelow, J. E.; Chattin, F. R.; King, L. J.; Ross, R. G. et al.
Partner: UNT Libraries Government Documents Department
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Coprocessing solvent-extraction flowsheet studies for LWR and FBR fuels

Description: Coprocessing solvent extraction studies using irradiated LWR and FBR fuels have indicated the need for an efficient feed clarification. A potentially useful filtration method for fulfilling this need has been demonstrated. Conditions necessary for the satisfactory use of unstabilized hydroxylamine nitrate (HAN) or nitrous acid as the reducing agent for Pu(IV) during reductive stripping operations have been defined. Both partial partitioning and total costripping operations have been demonstrate… more
Date: January 1, 1982
Creator: Collins, E. D.; Benker, D. E.; Bigelow, J. E.; Chattin, F. R.; King, L. J.; Lloyd, M. H. et al.
Partner: UNT Libraries Government Documents Department
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Solution Corrosion Group Quarterly Report for the Period Ending July 31, 1957

Description: The second All-Ti loop, 1OOA loop H, was placed in operation for more than 400 hr with UO/sub 2/SO/sub 4/ solution at 250 deg C and -- 1000 psi. A fourth test of the mockup of the Zircaloy-2--stainless steel transition joint used in the HRT reactor vessel was completed. The joint and bellows functioned properly and were leaktight. The series of long-term runs at 200, 250, and 300 deg C with solution proposed for use in the HRT was concluded. Stainless steel and Ti stress specimens exposed durin… more
Date: July 31, 1957
Creator: Griess, J. C.; Savage, H. C.; English, J. L.; Ulrich, W. C.; Buxton, S. R.; Neumann, P. D. et al.
Partner: UNT Libraries Government Documents Department
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