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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 hardnes… more
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 … more
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 establish… more
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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Single Particle Excitation Theory Of The Photonuclear Giant Resonance

Description: Calculations of the photonuclear giant resonance according to the Wilkinson model are presented in this report. In this model the giant resonance in the cross section for absorption of gamma rays by nuclei is ascribed to the excitation of large numbers of nucleons in closed shells. The model generally predicts correctly the integrated cross section for the giant resonance, bu the resonance energy is too low. Results are presented in a series of tables and formulas so that the integrated cross s… more
Date: July 30, 1963
Creator: Buskirk, F.
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 start… more
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 ener… more
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-inject… more
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 th… more
Date: July 26, 1963
Creator: Polomik, E. E. & Swan, C. L.
Partner: UNT Libraries Government Documents Department
open access

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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