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Study of Clay Shale Slopes Along the Panama Canal, Report 3: Engineering Analyses of Slides and Strength Properties of Clay Shales Along the Gaillard Cut

Description: "The results of the engineering studies and analyses which provide guidance on shear strength parameters applicable to the stability evaluation of existing slopes along the Gaillard Cut, the effects of future modifications, and evaluation of newly excavated slopes in clay shales are summarized in this report" (abstract). This report includes the appendices containing enginering data, characteristics of materials, analysis of past slides, active slopes, and hydrographic survey data.
Date: 1975
Creator: Banks, D. C.
Partner: UNT Libraries Government Documents Department

Physical Hydraulic Models: Assessment of Predictive Capabilities; Report 1: Hydrodynamics of the Delaware River Estuary Model

Description: Partial abstract: The purpose of this study is to define the reliability with which results of tests conducted in a physical model of the Delaware River Estuary can be used to predict the effects of modifications to the estuary. The Delaware River model at the Waterways Experiment Station was used to conduct tests to predict the effects of the navigation channel enlargement between Philadelphia and Trenton, and the results of the tests are compared with subsequent prototype data to determine the accuracy of the model predictions.
Date: June 1975
Creator: Letter, Joseph V., Jr. & McAnally, William H., Jr.
Partner: UNT Libraries Government Documents Department

Investigation of Nonmetallic Waterstops Report 9: Final Report of Effect of Exposure

Description: Final report describing the results of experiments to test samples of rubber, synthetic rubber, and polyvinylchloride (PVC) to determine their suitability for use in nonmetallic waterstops. During the tests, each of the samples was exposed to various conditions and environments before evaluation. This report discusses longer exposures of materials, to follow the previous report in the series discussing an evaluation of the same tests.
Date: June 1975
Creator: Houston, Billy J.
Partner: UNT Libraries Government Documents Department

Experiment DTA report for semiscale transparent vessel countercurrent flow tests

Description: Steady state air-water tests were performed as part of the Semiscale Blowdown and Emergency Core Cooling (ECC) Project to investigate downcomer countercurrent flow and downcomer bypass flow phenomena. These tests were performed in a plexiglass representation of the Semiscale pressure vessel which allowed changes to be madein the geometry of the upper annulus and downcomer for the purpose of investigating the sensitivity of downcomer and bypass flow to changes in system geometry. Tests were also performed to investigate the effects of two-phase inlet flows and different initial system pressures on countercurrent and bypass flow. Results for each test are presented in the form of computer printout of the measurements and of a summary of the pertinent calculated flow rates, pressures, and dimensionless volumetric fluxes. Descriptions of the test facility, instrumentation, operating procedures, and test conditions are also presented. An error analysis is presented for selected volumetric flux calculations. 10 references. (auth)
Date: October 1, 1975
Creator: Hanson, D.J.
Partner: UNT Libraries Government Documents Department

Quantitative evaluation of the RETIMAC system

Description: One means of raising the degree of protection afforded strategic special nuclear materials against theft and diversion is the installation of Real Time Material Control (RETIMAC) systems. The ability of RETIMAC to detect any covert attempt to steal special nuclear materials in a time frame that is adequate to contain subcritical quantities of special nuclear material within the boundaries of the material protection system and to maintain current knowledge of the quantity and location of all strategic special nuclear material was tested. A commercial-scale mixed oxide fuel fabrication plant was chosen for the study. (LK)
Date: June 10, 1975
Creator: Bain, E.E.; Fisher, R.H.; Gozani, T.; Harris, L. Jr.; Kendrick, H.; Kull, L.A. et al.
Partner: UNT Libraries Government Documents Department

Porous body model for predicting temperature distributions in wire wrapped fuel and blanket assemblies of a LMFBR

Description: Existing methods of thermal analysis of a wire wrapped rod bundle of a Liquid Metal Fast Breeder Reactor are based on the principle of subchannel analysis. A model for thermal transport in wire wrapped rod bundles is developed here. The model is similar in principle to the one which has long been successfully used in chemical engineering for heat and mass transfer in fixed beds of packed solids. By dividing the bundle into two predominant regions and applying the model of a porous body to a LMFBR assembly a simple procedure for calculating temperature distributions in LMFBR fuel and blanket assemblies has evolved. The results obtained were found to predict available data with as good a precision as do the more complex analyses. Correlations for the two empirical constants were obtained as functions of geometric parameters based on an extensive analysis of existing data. The LMFBR fuel assemblies operate in forced convection (negligible natural convection) under steady state conditions whereas the blanket assemblies may operate in forced or mixed convection (combined forced and free convection). Two different formulations of equations, corresponding to these two convection regimes, were developed using the same basic model. The calculation procedure for assemblies in forced convection (called ENERGY I) is considerably simpler than that (ENERGY II, ENERGY III) in mixed convection, where buoyancy effects become important. Therefore it is desirable to use ENERGY I for forced convection (although ENERGY II, III can also be used in forced convection, the computational times are fifteen fold greater). In order to determine when buoyancy effects become important a new criterion is developed. Given the power, the power skew, the operating and geometric characteristics of the bundle, the critical modified Grashof Number predicts when buoyancy effects become important. (auth)
Date: June 1, 1975
Creator: Khan, E.U.; Rohsenow, W.M.; Sonin, A.A. & Todreas, N.E.
Partner: UNT Libraries Government Documents Department

Decontamination and decommissioning of the EBR-I Complex. Final report

Description: This final report covers the Decontamination and Decommissioning (D and D) of the Experimental Breeder Reactor No. 1 (EBR-I) Complex funded under Contract No. AT(10-1)-1375. The major effort consisted of removal and processing of 5500 gallons of sodium/potassium (NaK) coolant from the EBR-I reactor system. Tests were performed to assess the explosive hazards of NaK and KO$sub 2$ in various environments and in contact with various contaminants likely to be encountered in the removal and processing operations. A NaK process plant was designed and constructed and the operation was successfully completed. Lesser effort was required for D and D of the Zero Power Reactor (ZPR-III) Facility, the Argonne Fast Source Reactor (AFSR) Shielding, and removal of contaminated NaK from the storage pit. The D and D effort was completed by 13 June 1975, ahead of schedule. (auth)
Date: July 1, 1975
Creator: Kendall, E.W. & Wang, D.K.
Partner: UNT Libraries Government Documents Department

Neutron-induced mutation experiments. Progress report, March 1, 1975-- February 29, 1976

Description: The relative mutagenic effectiveness of neutrons of different energies were compared with x radiation in mice and Drosophila oogonia employing X-linked recessive lethal and specific locus mutation tests. The energies and doses used were 0.68 MeV, 2 MeV, and 6 MeV (250 and 500$sup 0$R), and 15 MeV (250, 500, and 1000$sup 0$R). The data thus far collected from the recessive lethal test indicate that 0.68 MeV neutrons have the highest RBE among the energies tested, followed by 6 and 2 MeV. The specific locus mutation data also indicate the highest RBE for 0.68 MeV, followed respectively by 2 and 6 MeV. The 15 MeV data is as of now incompletely analyzed, as are some dose points of 2 and 6 MeV. (auth)
Date: November 1, 1975
Creator: Abrahamson, S.
Partner: UNT Libraries Government Documents Department

Fatigue-crack propagation behavior of Inconel 718

Description: The techniques of linear-elastic fracture mechanics were used to characterize the effect of several variables (temperature, environment, cyclic frequency, stress ratio, and heat-treatment variations) upon the fatigue-crack growth behavior of Inconel 718 base metal and weldments. Relevant crack growth data on this alloy from other laboratories is also presented. (33 fig, 39 references) (auth)
Date: September 1, 1975
Creator: James, L.A.
Partner: UNT Libraries Government Documents Department

Rain scavenging studies. Progress report No. 11

Description: The modeling of convective storm scavenging processes is going forward on two distinct fronts. The first of these relates to the microphysical processes, particularly to the study of their response to micro-dynamical components of the convective circulation. It is found that the droplet size spectra generated are responsive to variations of vertical velocity due to turbulence within the cloud and to humidity variations due to entrainment processes. Both sets of variations give responses that differ for different amplitudes and frequencies, i.e., rapid, small-amplitude eddies appear to enhance small-droplet development, whereas slow, large-amplitude oscillations tend to enhance large-droplet development. An allied study of the assumptions used in the microphysical equations is also being made. The second modeling effort is addressed to the problem of three-dimensional representation of convective dynamics. Equations are presented, and some of the problems under attack are discussed. (auth)
Date: May 1, 1975
Creator: Dingle, A.N.
Partner: UNT Libraries Government Documents Department

Internal friction in uranium

Description: Results are presented of studies conducted to relate internal friction measurements in U to allotropic transformations. It was found that several internal friction peaks occur in $alpha$-uranium whose magnitude changed drastically after annealing in the $beta$ phase. All of the allotropic transformations in uranium are diffusional in nature under slow heating and cooling conditions. Creep at regions of high stress concentration appears to be responsible for high temperature internal friction in $alpha$-uranium. The activation energy for grain boundary relaxation in $alpha$-uranium was found to be 65.1 +- 4 kcal/mole. Impurity atoms interfere with the basic mechanism for grain boundary relaxation resulting in a distribution in activation energies. A considerable distribution in ln tau$sub 0$ was also found which is a measure of the distribution in local order and in the Debye frequency around a grain boundary. (auth)
Date: November 20, 1975
Creator: Selle, J.E.
Partner: UNT Libraries Government Documents Department

Plutonium and cesium radionuclides in the Hudson River Estuary. Annual technical progress report, December 1, 1974--November 30, 1975

Description: We have obtained a large set of gravity cores from the Hudson Estuary through much of the ambient salinity range. A number of core sections have been analyzed for $sup 137$Cs, $sup 134$Cs, $sup 60$Co, and $sup 40$K by direct gamma counting, and for $sup 239$,$sup 240$Pu by alpha-spectrometry. The distribution of both $sup 137$Cs and $sup 239$,$sup 240$Pu indicates rapid accumulation in marginal cove areas and in the harbor region adjacent to New York City. The distribution of both $sup 137$Cs and $sup 239$,$sup 240$Pu in the sediments is quite similar in surface sediments, and the trends with depth in cores are also similar. The ratio of sediment $sup 239$,$sup 240$Pu to $sup 137$Cs throughout the sampled salinity range (0-20 $sup 0$/$sub 00$) approximates that in fallout, except near the nuclear reactor at Indian Point where releases of $sup 137$Cs result in a ratio lower (0.004 to 0.008) than typical of fallout (0.015). Measurement amounts of reactor-derived $sup 134$Cs, $sup 60$Co, and $sup 54$Mn are found in nearly all of the samples containing appreciable $sup 137$Cs. These samples were between 15 km upstream of Indian Point reactor site and the downstream extent of our sampling, 70 km south of the reactor. (auth)
Date: January 1, 1975
Creator: Simpson, H.J. & Williams, S.C.
Partner: UNT Libraries Government Documents Department

Elastic stability and vibration of toroidal magnets for fusion reactors. Final report

Description: The vibration and elastic stability of a set of discrete superconducting toroidal field magnets arranged to form a ''bumpy'' torus is examined. The mutual destabilizing magnetic forces between magnet pairs are calculated using a numerical differential inductance technique. It is shown that the mutual attractive magnetic forces can produce elastic buckling of the entire toroidal set. The vibration modes of the set are also found as functions of the coil current. The response of the set of magnets to an earthquake type motion of the toroidal base is calculated. The calculations have been incorporated in a computer code which accompanies the report. Measurements are made of the lateral stiffness of a flexible, planar, superconducting coil between two rigid coils in series. These tests show a dramatic decrease in the natural bending frequency with subsequent elastic instability or ''buckling'' at a critical value of the current in the coils. These observations support a magnetoelastic analysis which shows that proposed designs, of toroidal field coils for Tokamak fusion reactors, have insufficient lateral support for mechanical stability of the magnets. (auth)
Date: September 1, 1975
Creator: Moon, F.C. & Swanson, C.
Partner: UNT Libraries Government Documents Department

Hypothetical core disruptive accident

Description: The hypothetical core disruptive accident in an LMFBR is discussed under the following main headings: reactor dynamics; mechanical consequences; and post- accident heat removal. 79 references. (DCC)
Date: July 1, 1975
Creator: Simpson, D.E.
Partner: UNT Libraries Government Documents Department