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Mechanical Analysis of an SM 2 Blk IV restrained firing within a concentric canister launcher test unit

Description: The Office of Naval Research (ONR) and PMS512 have undertaken a program to develop a new Vertical Launching System (VLS) for future generation ships, such as the DD-21 Destroyer. The Naval Sea Systems Command Combat Weapons Program (NAVSEA 05K) and Naval Surface Warfare Center Dahlgren Division (NSWCDD) are working jointly with industry and universities to develop one such launcher design, the Concentric Canister Launcher (CCL). The basic CCL design consists of a tube made of two concentric cyl… more
Date: March 1, 1999
Creator: Kassner, M C; Kennedy, T C; Puttapitukporn, T & Rosen, R S
Partner: UNT Libraries Government Documents Department
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Characterization of options and their analysis requirements for the long-term management of depleted uranium hexafluoride

Description: The Department of Energy (DOE) is examining alternative strategies for the long-term management of depleted uranium hexafluoride (UF{sub 6}) currently stored at the gaseous diffusion plants at Portsmouth, Ohio, and Paducah, Kentucky, and on the Oak Ridge Reservation in Oak Ridge, Tennessee. This paper describes the methodology for the comprehensive and ongoing technical analysis of the options being considered. An overview of these options, along with several of the suboptions being considered,… more
Date: December 1995
Creator: Dubrin, J. W.; Rosen, R. S.; Zoller, J. N.; Harri, J. W. & Schwertz, N. L.
Partner: UNT Libraries Government Documents Department
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Elastic incompatibility stresses across planar and nonplanar grain boundaries in silver, aluminum, and zirconium applied to ductile fracture criteria under high triaxial stress

Description: Grain boundaries in a polycrystal imply elastic incompatibilities that can lead to stress states in the vicinity of the interface that are different from the macroscopic or applied stresses because the single crystal elastic properties are not all isotropic. This phenomenon is important as mechanical processes may operate at the microscopic level that would not be predicted based on the macroscopic stress state. This phenomenon has not been widely examined. One of the few studies that examined … more
Date: July 1, 1996
Creator: Roehnelt, R.; Kassner, M.E.; Kennedy, T.C. & Rosen, R.S.
Partner: UNT Libraries Government Documents Department
open access

High temperature properties of alloys being considered for design of a concentric canister launcher

Description: This report describes a study to determine the high temperature mechanical properties of several titanium alloys and to compare them with properties of AISI 316L stainless steel and ASTM A 387 structural steel. The steel materials are less costly to procure but exhibit good resistance to corrosion in seawater environments. Six titanium alloys were evaluated as candidate materials for use in a c Concentric Canister Launcher (CCL). Each titanium alloy was tested at three temperatures (68°, 2000°F… more
Date: June 1, 1998
Creator: Kassner, M E; Lowry, R W & Rosen, R S
Partner: UNT Libraries Government Documents Department
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Steady State Creep of Zirconium at High and Intermediate Temperatures

Description: Creep of zirconium and zirconium alloys has been labeled ''anomalous.'' Researchers often report that zirconium and its alloys never reach true steady state creep and have stress exponents that continuously change with stress and temperature. Many varied interpretations have been offered explaining the creep behavior of zirconium. Some have suggested that creep is diffusion controlled, while others maintain that creep is dislocation glide controlled. Cumulative zirconium creep data will be pres… more
Date: April 8, 2000
Creator: Rosen, R.S. & Hayes, T.A.
Partner: UNT Libraries Government Documents Department
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Modeling Creep Rupture of Zirconium Alloys

Description: Safe interim dry storage of spent nuclear fuel (SNF) must be maintained for a minimum of twenty years according to the Code of Federal Regulations. The most important variable that must be regulated by dry storage licensees in order to meet current safety standards is the temperature of the SNF. The two currently accepted models to define the maximum allowable storage temperature for SNF are based on a diffusion controlled cavity growth (DCCG) failure mechanism for the cladding. Although these … more
Date: April 8, 2000
Creator: Rosen, R.S. & Hayes, T.A.
Partner: UNT Libraries Government Documents Department
open access

Critical Analysis of Dry Storage Temperature Limits for Zircaloy-Clad Spent Nuclear Fuel Based on Diffusion Controlled Cavity Growth

Description: Interim dry storage of spent nuclear fuel (SNF) rods is of critical concern because a shortage of existing SNF wet storage capacity combined with delays in the availability of a permanent disposal repository has led to an increasing number of SNF rods being placed into interim dry storage. Safe interim dry storage must be maintained for a minimum of twenty years according to the Standard Review Plan for Dry Cask Storage Systems [1] and the Code of Federal Regulations, 10 CFR Part 72 [2]. Interi… more
Date: December 1, 1999
Creator: Hayes, T.A.; Rosen, R.S. & Kassner, M.E.
Partner: UNT Libraries Government Documents Department
open access

Depleted Uranium Hexafluoride Management Program. The technology assessment report for the long-term management of depleted uranium hexafluoride. Volume 1

Description: With the publication of a Request for Recommendations and Advance Notice of Intent in the November 10, 1994 Federal Register, the Department of Energy initiated a program to assess alternative strategies for the long-term management or use of depleted uranium hexafluoride. This Request was made to help ensure that, by seeking as many recommendations as possible, Department management considers reasonable options in the long-range management strategy. The Depleted Uranium Hexafluoride Management… more
Date: June 30, 1995
Creator: Zoller, J. N.; Rosen, R. S. & Holliday, M. A.
Partner: UNT Libraries Government Documents Department
open access

Depleted Uranium Hexafluoride Management Program. The technology assessment report for the long-term management of depleted uranium hexafluoride. Volume 2

Description: With the publication of a Request for Recommendations and Advance Notice of Intent in the November 10, 1994 Federal Register, the Department of Energy initiated a program to assess alternative strategies for the long-term management or use of depleted uranium hexafluoride. This Request was made to help ensure that, by seeking as many recommendations as possible, Department management considers reasonable options in the long-range management strategy. The Depleted Uranium Hexafluoride Management… more
Date: June 30, 1995
Creator: Zoller, J. N.; Rosen, R. S. & Holliday, M. A.
Partner: UNT Libraries Government Documents Department
open access

Thermal stability of Mo/Si multilayers

Description: The thermal stability of Mo/Si multilayers for x-ray mirror applications was investigated by annealing studies at relatively low temperatures for various times. The as-deposited and annealed multilayers were examined using conventional small and large angle x-ray diffraction, normal incidence x-ray reflectance measurements using a synchrotron source, selected area electron diffraction, and high-resolution electron microscopy. The as-deposited structure consists of pure layers of crystalline Mo … more
Date: July 1, 1991
Creator: Rosen, R.S.; Stearns, D.G. (Lawrence Livermore National Lab., CA (United States)); Viliardos, M.A.; Kassner, M.E. (Oregon State Univ., Corvallis, OR (United States). Dept. of Mechanical Engineering) & Vernon, S.P. (Vernon Applied Physics, Torrance, CA (United States))
Partner: UNT Libraries Government Documents Department
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Creep strains predicted from constitutive equations for Zircaloy-clad spent fuel rods

Description: Integrity of a high percentage of the Zircaloy (zirconium-alloy) clad spent fuel rods during extended dry storage is a design consideration of the storage system. Maintaining cladding integrity after permanent disposal placement may also be desired, although other barriers will be engineered to contain the radioactive waste. The limits to the temperatures the Zircaloy tubes can sustain over extended times are principally determined by creep at stresses (from internal gas pressure) and temperatu… more
Date: November 1, 1994
Creator: Rosen, R. S. & O`Connell, W. J.
Partner: UNT Libraries Government Documents Department
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Quench sensitivity of hot extruded 6061-T6 and 6069-T6 aluminum alloys

Description: The purpose of this study is to investigate the quench sensitivity of mechanical properties of hot extruded 6061 and 6069 aluminum alloys. The relationship between mechanical properties and quench delzty time at various temperatures between 200-500 C was determined. It was concluded that the 6069-T6 was somewhat more quench sensitive than 6061, which may be consistent with the composition difference.
Date: August 8, 2000
Creator: Bergsma, S C; Kassner, M E; Li, X & Rosen, R S
Partner: UNT Libraries Government Documents Department
open access

Recent developments in understanding five-power-law creep in metals

Description: This work describes recent advances on the effects of subgrain boundaries on elevated-temperature plasticity. Particular attention is devoted to recent developments regarding internal back-stresses. This will include discussions of recent convergent beam electron diffraction (CBED) experiments on metals to evaluate internal stresses in association with dislocation heterogeneities.
Date: April 8, 2000
Creator: Kassner, M E; Perez-Prado, M-T; Rosen, R S & Bergsma, S C
Partner: UNT Libraries Government Documents Department
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