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Calculation of the Doppler Coefficient Plutonium-Oxide-Fueled Fast Reactors

Description: Report issued by the APDA over studies conducted on Doppler coefficient fast reactors. Calculations, methods, and results of the studies are presented. This report includes tables, and illustrations.
Date: November 1, 1963
Creator: Fischer, E. A.
Partner: UNT Libraries Government Documents Department

Two-Facility Approach to Investigations of Fast Reactor Meltdowns

Description: Report issued by the APDA over studies conducted on hypothetical fast reactor meltdown accidents. As stated in the summary, "the purpose of this study is to investigate the technical feasibility of conducting fast reactor meltdown experiments to determine a more realistic maximum accident and to provide a better evaluation of fast reactor safety" (p. 7). This report includes tables, and illustrations.
Date: January 15, 1963
Creator: Doyle, T. A.; Page, E. M.; Nicholson, R. B.; Hagstrom, J. T. & Nims, J. B.
Partner: UNT Libraries Government Documents Department

Study of Requirements and Suitability of Available Reactors for Fast Fuel Tests

Description: Report issued by the APDA over studies conducted on the requirements of reactors for fuel testing. As stated in the summary, "the purpose of this study is to determine the requirements for radiation space for fast reactor fuel testing and to determine the capability of existing Commission and private test and power reactors to meet these requirements" (p. 7). This report includes tables, and illustrations.
Date: February 23, 1963
Creator: Doyle, T. A.; Duffy, J. G.; Jens, W. H.; McHugh, W. E.; Page, E. M. & Warberg, H. S.
Partner: UNT Libraries Government Documents Department

Study of Fast Reactor Meltdown Accidents Using Simulant Materials

Description: Report issued by the APDA over studies conducted on reactor meltdown accidents. The studies incorporated the use of simulation materials. Methods and results of the studies are presented and discussed. This report includes tables, illustrations, and photographs.
Date: August 31, 1963
Creator: Huebotter, P. R.
Partner: UNT Libraries Government Documents Department

Lithology and Reservoir Properties of the Big Lime, Keener, Big Injun, Weir, and Berea Horizons, Spruce Creek Oilfield, Ritchie County, West Virginia

Description: Report issued by the Bureau of Mines on the lithology of oilfields in Ritchie County, West Virginia. The different properties and characteristics of the core samples found in Ritchie County are presented, and compared. This report includes tables, and a map.
Date: 1963
Creator: McCord, Wallace R. & Eckard, William E.
Partner: UNT Libraries Government Documents Department

Bovill Clay and Sand Deposit, Latah County, Idaho: Geology, Minerology, and Beneficiation Tests

Description: Report issued by the Bureau of Mines on the clay-silica deposits found in Bovill, Idaho. As stated in the abstract, "the geology, mineralogy, beneficiation, and potential uses of the clay and quartz fractions of the Bovill deposit are described" (p. 1). This report includes tables, graphs, photographs, and maps.
Date: 1963
Creator: Kelly, Hal J.; Carter, George J. & Todd, George H.
Partner: UNT Libraries Government Documents Department

Properties of Compounds in Coal-Carbonization Products

Description: Report issued by the Bureau of Mines over studies conducted on the compounds of coal carbonization. Descriptions of these compounds are discussed. This report includes tables.
Date: 1963
Creator: Anderson, Hazel C.
Partner: UNT Libraries Government Documents Department

Petroleum-Engineering Study of the Hall-Gurney Oilfield, Russell County, Kansas

Description: Report issued by the Bureau of Mines over petroleum-engineering studies on the Hall-Gurney oilfield. As stated in the introduction, "this report describes the development, oil recovery, and potentialities of productive formations in the Hall-Gurney field, Russell County, Kansas" (p. 1). This report includes tables, maps, and illustrations.
Date: 1963
Creator: Riggs, C. H.; Heath, Larman J.; Ward, Don C. & Huff, Ray V.
Partner: UNT Libraries Government Documents Department

Design and Applications of Some Mathematical Models for Mine-Systems Analysis

Description: Report issued by the Bureau of Mines over mining systems. As stated in the introduction, "the purpose of this publication is to show possible application, within the field of mining, of some innovations to methods of analysis that have been developed and improved in recent years" (p. 2). This report includes tables, graphs, and illustrations.
Date: 1963
Creator: Hewlett, Richard F. & Redmon, D. E.
Partner: UNT Libraries Government Documents Department

HANDBOOK FOR THE NANO-SECOND ELECTRON ACCELERATOR (NSEA)

Description: As an aid to prospective users of the device, the electron accelerator, the detection system, and the readout equipment are described; and the operational procedures followed are explained. Maintenance instructions are also given, as are diagrams of many components. The apparatus was designed mainly for studying scintillation decay times in the nsec region. (D.C.W.)
Date: March 1, 1963
Creator: Mroz, E.A.; Buck, W.L.; Swank, R.K. & Phillips, H.B.
Partner: UNT Libraries Government Documents Department

Neutron Kinetics for Reflected Compact Reactors on Short Periods

Description: The common seventh group approximation for treating the effect of neutron delay due to reflector slowing down and thermalization is presented. Modifications appropriate when reactivity changes are produced by reflector movements are introduced. An improved formulation, allowing distinctions between several different groups of slowing down and thermalizing neutrons, is presented. This formulation is shown to reduce to the seventh group approximation for the case of one atypical neutron group, providing the population and reaction rate of the group are small in comparison to the total neutron population and reaction rate. (auth)
Date: June 1, 1963
Creator: Miller, J.
Partner: UNT Libraries Government Documents Department

Fuel Cycle Program. A Boiling Water Reactor Research and Development Program. Eleventh Quarterly Progress Report, January-March 1963

Description: Even though VBWR shutdowns were required for location and removal of five failed fuel assemblies (HPD Program), the increase in fuel exposure was good. Fuel exposures wili pass the values at which cold worked stainless steel cladding was failing under the HPD Program. Failure of the 0.005-inch cold worked stainless steel clad fuel rods in assembly 8L was traced to strain cycling fatigue. A study of tapered fuel rods indicates a potential advantage for us of a variable water/fuel ratio along the flow channel. Natural circulation tests in the hydraulic stability loop were conducted over a range of conditions from stable, to oscillatory with exponential decay, to self-sustaining oscillation of constant amplitude, to unstable oscillations with divergent amplitude. The response to impulses in power input shows the effect of the time delay for transporting steam voids up through the riser. The data permit calculation of oscillation frequency, damping coefficient, time lags, and show the magnitude and character of pressure and velocity changes. The data, which have an experimental scatter of plus or minus 10% maximum, show that burnout heat fiux: decreases with increasing flow up to 2 x 10/sup 8/ lb/hr-ft/sup 2/; has a maximum for hydraulic diameter between 0.25 and 0.5 inch; and decreases for pressure increases between 600 to 1400 psi. A correlating equation for the data is given. The data are compared to results of others. Tests of special geometries show that the burnout heat flux: decreases 22 to 50% when the heated rod is within 0.033 inch of the channel wall; is unchanged upstream of a plate-type spacer; decreases 35 to 50% when the rod surface is roughened by sandblasting; is increased 20 to 40% by use of a rough liner. The four-rod test section is operating satisfactorily and 17 critical heat fiux data points are …
Date: April 1, 1963
Creator: Howard, C.L. comp.
Partner: UNT Libraries Government Documents Department

Feasibility and Conceptual Design for the Step Loss of Coolant Facility

Description: A summary of studies conducted on the pressurizedwater reactor loss-of- coolant accident is presented, and an experimental safety program is proposed. The various phenomena involved in the loss-of-coolant accident, related research and development programs, assumptions currently used to predict the various physical phenomena, and the general approach to be used in conducting the safety tests are discussed. In order to accomplish the loss-of-coolant experimental safety program, a dry containment test facility is proposed for construction at the Test Area North of the National Reactor Testing Station in Idaho. The site selection utilizes existing support facilities suited for performing nuclear safety tests requiring experiment assembly areas and post-test analytical examination of the irradiated nuclear components. (auth)
Date: April 24, 1963
Creator: Wilson, T. R.; Hauge, O. M. & Matheney, G. B.
Partner: UNT Libraries Government Documents Department

FACTORS FOR ONE-SIDED TOLERANCE LIMITS AND FOR VARIABLES SAMPLING PLANS

Description: Tables are given of a quantity k that is used to define single-sample variables sampling plans and one-sided tolerance limits for a normal distribution. The probability is gamma that at least a proportion P of a normal population is below x + ks, where x has a normal distribution with mean and variance re p- terphenyl /sup 2//n and fs/sup 2// re p-terphenyl /sup 2/ has a chi-square distribu tion with f degrees of freedom. The quantity k just described corresponds to a percentage point of the noncentral tdistribution and is extensively tabulated. Tabulations of other functions computed from the noncentral t-distribution and various expected values are also given. Many other applications are discussed and various approximations compared. One section gives the mathematical derivations and there is an extensive bibliography that was cross referenced to several indices of mathematical and statistical literature. 82 references. (auth)
Date: March 1, 1963
Creator: Owen, D.B.
Partner: UNT Libraries Government Documents Department

POWER APPLICATIONS OF RADIONUCLIDES

Description: The development and uses of SNAP power supplies which derive their energy from the decay of radioactive isotopes are discussed. (N.W.R.)
Date: January 1, 1963
Creator: Bloom, J.L.
Partner: UNT Libraries Government Documents Department

PLASMA DIAGNOSTICS WITH SHORT ELECTROMAGNETIC PULSES

Description: The propagation of short electromagnetic pulses in an ionized medium and the reflection of transient pulses from bounded ionized regions is discussed. Analyticai expressions for transient oscillations in reflected and propagated electromagnetic fields excited by a unidirectional pulse are derived for certain simple cases. The transient oscillations show a periodicity that is directly related to the plasma frequency and are useful for nearly instantaneous plasma diagnostics. An experiment is described in which the reflection and transmission of unidirectional pulses of approximately 1-nanosecond duration is observed in the afterflow of a coaxial discharge tube. In addition to the dispersion of the quasi TEM mode in the coaxial test tube, a transient oscillation with much lower periodicity is also observed and is interpreted as arising from a surface-wave propagating near the interface between glass walls and the annular ionized region. This surface-wave propagates only at frequencies below the plasma freguency of the ionized region, and its application for diagnostics of dense plasmas is indicated. (auth)
Date: July 1, 1963
Creator: Schmitt, H.J.
Partner: UNT Libraries Government Documents Department

RESEARCH DESIGNED TO EVALUATE Zr-2.5Nb AND Zr-2.5Nb-0.5Cu ALLOYS FOR DELAYED FAILURE HYDRIDE SUSCEPTIBILITY. Quarterly Report No. 1, October 15, 1962-January 14, 1963

Description: The purpose of this program is to determine the extent to which Zr-2.5Nb and Zr-2.5Nb --0.5Cu exhibit delayed failure (static fatigue) under various conditions of hydrogen content, heat treatment, and ambient temperature. Specimens are hydrogenated to 200 ppm or 500 ppm by means of a modified Sieverts apparatus, heat treated or cold reduced, and then evaluated in dynamic tensile and delayed failure tests under a certain set of conditions. At the present time, data are insufficient to form any conclusions regarding static fatigue behavior of these alloys. (auth)
Date: January 21, 1963
Creator: Weinstein, D. & Holtz, F.C.
Partner: UNT Libraries Government Documents Department

Thermal Hydraulic Performance Characteristics of EBWR (0 to 100 Mwt)

Description: The modifications of the EBWR internals for operation at higher power included: redesign of riser, relocation and resizing of feed-water injection ring and inlet nozzle, enclosing the core with a cylindrical shell and providing a tight closure between riser and core, and redesign of the steam-discharge system. The volume fraction of steam voids, recirculation flow rate, subcooling, liquid level, steam carryunder in downcomer, and liquid carryover in effluent stream were determined. Instrumentation include differential pressure probes, Stauschiebe tubes, and thermocouples. Tests indicated that the performance characteristics of the EBWR are governed directly by steam carryunder in the downcomer, liquid carryover in the effluent stream, and, indirectly, by the location of the true water- steam interface in the vessel. (M.C.G.)
Date: May 1, 1963
Creator: Petrick, M. & Spleha, E.A.
Partner: UNT Libraries Government Documents Department

1000 MWE Closed Cycle Water Reactor Study Volume II

Description: This report includes the nuclear evaluation that has been conducted for the purpse of studying those problem areas which are expected to increase in severity as the core size is increased to produce 1000 MWE.
Date: March 1, 1963
Partner: UNT Libraries Government Documents Department
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