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Equipment for Hardness Testing at Elevated Temperatures

Description: The design and testing procedures of two elevatedtemperature hardness testers are described. One device uses a Rockwell tester with a large vertical capacity and a load range of 15 to 150 kg. The tester is equipped with a 900 deg C heating chamber which maintains an argon atmosphere over the specimen and can be laterally displaced by a cross-feed mechanism to allow repeated hardness readings to be made on the same specimen. The second instrument is a microindentation hardness tester for hardness determinations to a maximum temperature of 1000 deg C in vacuum of 10/sup -4/ to 10/sup -5/ torr. A deadweight loading system with a 136-deg diamond pyramid (Vickers) indenter, capable of delivering static loads between 0.150 and 3 kg, is contained within the vacuum chamber to avoid calibration problems that arise when loads are applied from outside the vacuum system. The microindentation hardness tester allows up to 100 determinations to be made on a single specimen without opening the test chamber. The applicability of the testers is illustrated by elevatedtemperature hardness measurements on several commercial alloys, a group of niobium-vanadium alloys, and by the changes in hardness occurring at the transformation temperatures of iron and steel. Hardness values of Haynes alloy No. 25 were determined at the temperatures of aging and are shown to be different from those obtained with the customary method of investigating age hardening. The testing is currently being used to aid and accelerate the development of alloys with desirable high-temperature properties. (auth)
Date: July 31, 1963
Creator: Hallerman, G. & Gray, R.J.
Partner: UNT Libraries Government Documents Department
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Fireball yield from fractional intensity diameters

Description: It is desired to develop an empirical formula of the type Y=KD[sup n] where Y is the yield in kilotons and D is the `effective diameter` in feet corrected for temperature and pressure variations if necessary.
Date: July 31, 1963
Creator: Gellert, E. R.
Partner: UNT Libraries Government Documents Department
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Maritime Gas-Cooled Reactor Program, Quarterly Progress Report: April-June 1961

Description: Quarterly report discussing activities of the Maritime Gas-Cooled Reactor (MGCR) Program and the progress of the Program in developing a nuclear-powered marine propulsion system utilizing a high-temperature, gas-cooled nuclear reactor, close-cycle gas-turbine power plant.
Date: July 31, 1963
Partner: UNT Libraries Government Documents Department
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Pressure Pulses in Rapid Transient Boiling

Description: Investigation of whether the multi-thousand psi pressure pulses that occurred in the BORAX-I and SPERT-I destructive power excursion could have been generated by thermal mechanisms in the geometries of unmolten reactor cores. These pressure pulses were "at least as high as 6,000 psi, and probably higher than 10,000 psi " in BORAX I, and "between 3,000 and 4,000 lb/in" in SPERT I. An experimental investigation was undertaken of pressure pulse generation by purely thermal means.
Date: July 31, 1963
Creator: Wright, R. W.
Partner: UNT Libraries Government Documents Department
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REPORT OF THE QUALIFICATION TESTING OF SNAP 10A FUSISTORS

Description: Qualification testing of SNAP 10A fusistors was performed. Test operations included: visual inspection, insulation resistance, dielectric strength, and d-c resistance testing prior to subjecting the fusisters to environmental testing; opening-time testing prior to, during, and following vacuum and temperature testing; and insulation resistance, dielectric strength, and d-c resistance testing following environmental applications of temperature, vacuum, and sinusoidal vibration. (auth)
Date: July 31, 1963
Creator: Holtwick, J.S. III & Nowell, V.P.
Partner: UNT Libraries Government Documents Department
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EDP Procedures in Technical Library Operations

Description: Systems for circulation control, book ordering, journal renewal, printing a book catalog, preparing monthly acquisitions lists.
Date: July 30, 1963
Creator: Griffin, Hillis L.
Partner: UNT Libraries Government Documents Department
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MOUND LABORATORY PROGRESS REPORT FOR JULY 1963

Description: 8 7 6 2 ; 7 4 7 6 : 7 8 : : ; half life of 3.781 plus or minus 0.010 years based on calorimetric measuiements. The calorimetric assay of the sample will be continued ior several years to decrease the probable error. The decay scheme for /sup 209/Po--/sup 209/Po/ isitopic mixtures is being determined. The gamma spectrum is being studied using two sources of different isotopic composition. Definite peaks were established at 76, 260, 300, 575, and 9l0 kev. Various multiple coincidence experiments indicated that the 300- and 575-kev photons and the 76-kev x-ray are in triple coincidence. Relative intensities of the various gamma rays from the two different sources indicated that the 575-kev photon is associated with /sup 208/ Po decay, while the 260- and 910-kev states are attributed to /sup 209/Po. A theoretical estimate of the partial alpha half life for /sup 208/Po decay to the 2+ level in /sup 204/Pb (at 0.899 Mev) was made. This value (2.5 x 10/sup 6/ years) was determined graphically by extrapolation to an alpha particle energy of 4.2l1 Mev. /sup 209/Po--/sup 2o9/Po sources are being prepared for the investigation of the internal conversion electron spectra of these isotopes. Ion exchange techniques are being studied for the separation of /sup 227/Ac from / sup 227/Th, /sup 223/R a, and /sup 226/Ra. Naturally occurring lanthanum, thorium, and barium are being used as experimental substitutes. Composite elution curves indicated that lanthanum and /sup 232/Th can be successfully isolated with 2 M HCl, 3 M HNO/sub 3/, and ammonium acetate as elutrients. A purified form of the original Dowex 50W-X8 column packing matenial was used; the new material (AG-50W-X8) reduced tailing on the elution curves. /sup 228/Th was tentatively assigned a half life of 1.9132 years with an internal probable error of …
Date: July 30, 1963
Creator: Eichelberger, J.F.; Grove, G.R. & Jones, L.V.
Partner: UNT Libraries Government Documents Department
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Pathfinder Atomic Power Plant. End Closure Development for Low Enrichment Superheater Fuel Rods

Description: Research on a welding process for closing the ends of pathfinder fuel elements is reported. Optimum parameters for certain variables (amperage, weld travel, preheat, etc.) affecting weld quality were determined, and two modified end cap designs were investigated and found to reduce weld sensitivity to certain variables. Use of chills on the fuel tube greatly improved weld puddie geometry and microstructure. Optimum weld parameters for rods containing UO/sub 2/ fuel were experimentally established. (D.C.W.)
Date: July 30, 1963
Creator: Boschke, R. A. & Wiggins, R. J.
Partner: UNT Libraries Government Documents Department
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A Perturbation Method for Solving the Angle Dependent Nucleon-Meson Cascade Equations

Description: A method is described for obtaining an approximate solution to the equations describing a nucleon-meson cascade by using the angular dependence of the secondary particle production kernels as a perturbation. The usefulness of the method lies in the fact that in a slab geometry the equations that must be solved numerically are essentially the same as those that are used in the straight-ahead approximation and have been solved previously. (auth)
Date: July 30, 1963
Creator: Alsmiller, R. G., Jr. & Alsmiller, F. S.
Partner: UNT Libraries Government Documents Department
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Production test IP-603-I evaluation of accidental fuel flushing potential D-DR reactors

Description: This purpose of this test is to acquire data to support further studies aimed at determining whether a normal column of I&E enriched fuel elements or a normal column of natural fuel elements can be flushed from a process tube with the crossheader valved down to shutdown position if the front riser pressure is raised to normal operation pressure.
Date: July 30, 1963
Creator: Hollifield, P. J. & George, D. K.
Partner: UNT Libraries Government Documents Department
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The Strain Aging and Heat Treatment Properties of N-Reactor Connector Tubes

Description: Report regarding the determination of "the susceptibility to strain aging and the effect of stress-relief annealing on the properties of N-reactor connecting tubes made from ASTM A-106 Grade B high carbon steel" (p. 2).
Date: July 30, 1963
Creator: Pessl, H. J.
Partner: UNT Libraries Government Documents Department
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The Activity Coefficients of Hydrochloric Acid and Sodium Chloride in Hydrochloric Acid-Sodium Chloride Mixtures

Description: The activity coefficients of HCl and NaCl in HCl--NaCl mixtures were computed from literature data. The calculations are based on the observation that at constant ionic strength and temperature the logarithm of the activity coefficient of HCi in HCl--NaCl mixtures varies linearly with NaCl concentration. (auth)
Date: July 29, 1963
Creator: Lietzke, M. H. & Stoughton, R. W.
Partner: UNT Libraries Government Documents Department
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NRX-B Module Bending Analysis

Description: A description is presented of a preliminary bending analysis of three module configurations designed for the 19-hole Kiwi-B4-type fuel element.
Date: July 29, 1963
Creator: Eggers, A.
Partner: UNT Libraries Government Documents Department
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Recommended emergency procedure for extended outage at all IDP production reactors

Description: If for an unspecified reason it becomes necessary to shut down all eight production reactors for an extended period exceeding normal outage times, the following procedures are recommended. These procedures have been devised to render the maximum safe situation short of complete core discharge and to enable as efficient a reactor startup as possible following the outage. Specific topics include: general safety, startup efficiency, detailed shutdown procedure of reactor and water plant, and startup procedure. (GHH)
Date: July 29, 1963
Partner: UNT Libraries Government Documents Department
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Tabulated Values of Scattered Gamma-Ray Fluxes in Water Interpolated From Moments Method Calculations

Description: Tables of scattered gamma-ray fluxes in water that are suitable for integration over source spectra were generated on the IBM-7090 computer by Lagrangian interpolation of moments method results for point isotropic gamma-ray sources. Values of the fluxes were obtained for a consistent set of scattered gamma-ray energies taken in steps of 0.1 Mev from 0.1 to 1.0 Mev and in steps of 0.25 Mev from 0.25 to 10 Mev. One table was obtained for each scattered energy for various values of the source energy and of the distance from the source in mean free paths. Tables were then generated in which the distance from the source was converted from mean free paths to centimeters. The latter set may be integrated over any source spectrum to obtain the flux of scattered gamma rays in water, and, with small error, in any material in which the cross section is dominated by the Compton scattering cross section. This includes the low-Z materials such as aluminum and air. (auth)
Date: July 29, 1963
Creator: Trubey, D. K.
Partner: UNT Libraries Government Documents Department
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Engineering Features of DCX-2

Description: The DCX-2 is a large, complex experimental apparatus. Its aim is the generation of a hot, dense plasma by the injection and dissociation of 600-kev hydrogen molecNoneular ions in a magnetic-mirror field. For facilitating this process, the molecular ions are given a long path in the machine, and the ion- pumping action of the plasma is used to maintain the vacuum. The major component systems of the apparatus are the ion source and accelerator, highvoltage power supply, magnet system, beam-injection duct, vacuum system, and dissociating arc. The design, construction, and performance of each component system, the constructional features not peculiar to any one component, and the instruments and techniques available for plasma study are described. (auth)
Date: July 26, 1963
Creator: Bell, P. R.; Culver, J. S.; DeCamp, S. M.; Ezell, J. C.; Kelley, G. G.; Lazar, N. H. et al.
Partner: UNT Libraries Government Documents Department
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High Power Density Development Project: Potter Meter Calibration and Instrumented Fuel Bundle Pressure Drop

Description: Summary: Technical report describing the testing of eight Potter Meters, for metering inlet flow and measuring exit steam qualities in the Consumers Big Rock Point Instrumented Fuel Assemblies, were individually calibrated for flow and pressure drop up to 500 gpm in the low temperature (130 F) fluid flow facility. The flow calibration comparison made with an ASME orifice installation, agreed to within + - 1 percent among seven of the meters, and meter Serial No. 8 was 2.8 percent lower than the others. Pressure drop among the meters was within about 5 percent. Locked rotor pressure drop data was obtained on one meter. A fully instrumented fuel bundle was tested in the low temperature facility and pressure drop data obtained for the tieplates and meters, spacers, and channel rods. A mock-up of the exit end of the instrumented fuel bundles, composed of 1 foot of fuel rods, tieplate, and Potter Meter was tested in the High Pressure Heat Transfer Facility. Data was obtained for single- and two-phase calibration of total flow and exit steam quality in an instrumented bundle. Each meter was operated, for a minimum of 6-8 hours after bearing modifications necessitated by seizure of the rotors, in the High Pressure Facility under conditions of 1000 psi and qualities of about 5-6 percent to verify operation and obtain some run-in time before reactor installation. A total of 655 hours of test and run-in time was made on all eight meters.
Date: July 26, 1963
Creator: Polomik, E. E. & Swan, C. L.
Partner: UNT Libraries Government Documents Department
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Integral Neutron Thermalization. Quarterly Progress Report for the Period Ending June 30, 1963

Description: Decay constant and modal analysis measurements were performed in a U/sup 235/-water critical assembly, and infinitemedium neutron spectra in water poisoned with a 1/V absorber were measured at various pressures and temperatures. The results were compared with theoretical predictions. Neutron penetration of water shielding was also measured. Theoretical work involved models and codes for neutron thermalization in ZrH, Be, and water. (D.C.W.)
Date: July 26, 1963
Creator: Young, J. C.; Beyster, J. R.; Brown, J. R.; Houston, D. H.; Kirkbride, J.; Koppel, J. U. et al.
Partner: UNT Libraries Government Documents Department
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