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An Analytical Model for Predicting Cross-Country Vehicle Performance, Appendix D: Performance of Amphibious Vehicles in the Water-Land Interface (Hydrologic Geometry)

Description: Summary: "Forty tests were conducted with two amphibious tracked vehicles and one amphibious wheeled vehicle at Eglin Air Force Base, Fla., and near Khon Kaen, Thailand, to determine the vehicles' capabilities for exiting closed bodies of water. Empirical relations, based on the data collected in this study and in previous studies, are presented to support the conclusions that performance of amphibious tracked and wheeled vehicles (in terms of "go-no go") in the water-land interface can be correlated with soil strength (expressed as average cone index of the 0- to 6-in. soil layer), and that the slope-climbing ability in the water-land interface of the tracked vehicles tested compares favorably with that of the same vehicles operating on land surfaces of similar soil composition and consistency" (p. ix).
Date: February 1970
Creator: Blackmon, Claude A.; Stinson, B. G. & Stoll, J. K.
Partner: UNT Libraries Government Documents Department

Foundation Investigations, NASA Mississippi Test Facility, Report 4: Dynamic Behavior of Piling During Initial Test Firings on the S-IC and S-II Test Complexes

Description: Report on test firings conducted by a U.S. National Aeronautics and Space Administration (NASA) test facility. "The Mississippi Test Facility, located approximately 40 miles northeast of New Orleans, La., is the site of the test stands built to test the first and second stages of the Saturn V space vehicle. At the request of the U. S. Army Engineer District, Mobile, plans were developed for instrumenting the test stands to obtain data on foundation base pressures, lateral wall pressures, and pile loads during and after the actual test firings of the Saturn V engines" (p. xi).
Date: June 1970
Creator: Fowler, Jack
Partner: UNT Libraries Government Documents Department

Correlation of Backswamp Sediments: Atchafalaya Test Section 6, Atchafalaya Levee System, Louisiana

Description: This report describes the results of a series of tests on soil borings taken in Atchafalaya Test Section VI, a 2000-ft-long portion of the Atchafalaya Basin Protection Levee System in south-central Louisiana. The samples were tested to interpret the depositional layers in the foundations soils and to determine various engineering properties.
Date: May 1970
Creator: Krinitzsky, E. L.
Partner: UNT Libraries Government Documents Department

Survey of Gulf Coast Structural Damage Resulting from Hurricane Camille, August, 1969

Description: This report describes damage to structures by Hurricane Camille in qualitative terms, and with photographs. The investigation was carried out by a team sponsored by the Office of Civil Defense, and it includes conclusions and recommendations.
Date: 1970
Creator: Criswell, Marvin E. & Cummins, Reid S.
Partner: UNT Libraries Government Documents Department

Short- and Long-Time Deflections of Reinforced Concrete Flat Slabs

Description: Summary: "This report summarizes the results of a field investigation to determine the short- and long-time deflections and concrete strains in an Army barracks flat-plate structure at Fort Hood, Killeen, Texas. Due to the rather great slab thickness of 9 in., corresponding to an L/T ratio of approximately 28, all observed deflections were small and in no instance exceeded 0.022 ft, or about 1/800 of the shorter span, during the 45-month observation period, in spite of an early temporary construction load estimated to have been almost 30 percent in excess of the total design load. The measured short-time deflections under various loading conditions compared reasonably well with deflections predicted by use of the ersatz frame analysis method" (p. ix).
Date: February 1970
Creator: Geymayer, H. G. & McDonald, J. E.
Partner: UNT Libraries Government Documents Department


Description: The objective of the Reactor Physics Quarterly Report is to inform the scientific community in a timely manner of the technical progress made on the many phases of reactor physics work within the laboratory. The report contains brief technical discussions of accomplishments in all areas where significant progress has been made during the quarter.
Date: May 1, 1970
Creator: Schmid, L. C.; Clayton, E. D. & Heineman, R. E.
Partner: UNT Libraries Government Documents Department


Description: Fault tree techniques have been used to identify possible failure paths within the NPTR which could lead to core disassembly. The analysis o f the various faults has led to formulation of design requirements, protective system requirements, and administrative restraints required to prevent accidents from these faults. Transient analyses were performed using the heat transfer-nuclear kinetics codes, Nutiger-II, FORE-II, and MELT-II . To verify results, intercomparison studies were made between the codes. The codes were i n good general agreement. Each code was found to exhibit different advantages and disadvantage. Inherent reactivity feedback effects were assessed in the analysis. With the assumed core parameters, there appears to be sufficient Doppler to prolong a nuclear transient to allow protective action to prevent fuel from melting. The use of average values of the feedback coefficients smeared over the entire core does not appear to be an acceptable method with spacially dependent temperatures. In the thermal analysis, the fuel pin gap coefficient and sodium film coefficient do not appear to be highly sensitive parameters for transient analysis. Power transients resulting from reactivity insertions of from 2$/sec to 20$/sec have been examined in detail. Sodium will be molten before fuel melting occurs for accidents within this range. For the smaller ramp rates (< 4$/sec), sodium nay even reach vaporization temperatures before any fuel melts. Power transients terminated by effective protective action were investigated. It i s believed p o s s i b l e t o design a scram system, with the . present state of the art, to prevent sodium from melting for a reactivity ramp up to at least 6$/sec. This same system would prevent fuel melting for a reactivity ramp up to 15$/sec. Sodium thermal expansion will play a very important role in a core disassembly. When the average sodium ...
Date: January 1, 1970
Creator: Schade, A. R.
Partner: UNT Libraries Government Documents Department