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Influence of strain rate and temperature on the mechanical behavior of beryllium

Description: The compressive stress-strain response of three grades of beryllium were studied as a function of strain rate and temperature. Grades S2OOD, E, and F represent a historical perspective of beryllium processing from the 1960`s through 1990`s technology. The purpose of this study was to measure the mechanical behavior of beryllium over a range of deformation conditions for constitutive model development and to obtain microstructural evidence for deformation mechanisms. The compressive stress-strai… more
Date: July 1, 1997
Creator: Blumenthal, W. R.; Carpenter, R. W.; Cannon, D. D.; Abeln, S. P. & Gray, G. T., III
Partner: UNT Libraries Government Documents Department
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Background studies in support of a feasibility assessment on the use of copper-base materials for nuclear waste packages in a repository in tuff

Description: This report combines six work units performed in FY`85--86 by the Copper Development Association and the International Copper Research Association under contract with the University of California. The work includes literature surveys and state-of-the-art summaries on several considerations influencing the feasibility of the use of copper-base materials for fabricating high-level nuclear waste packages for the proposed repository in tuff rock at Yucca Mountain, Nevada. The general conclusion fro… more
Date: June 1, 1990
Creator: Van Konynenburg, R. A.; Kundig, K. J. A.; Lyman, W. S.; Prager, M.; Meyers, J. R. & Servi, I. S.
Partner: UNT Libraries Government Documents Department
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Shock compression and quasielastic release in tantalum

Description: Previous studies of quasielastic release in shock-loaded FCC metals have shown a strong influence of the defect state on the leading edge, or first observable arrival, of release wave, due to large density of pinned dislocation segments behind the shock front, their relatively large pinning separation, and a very short response time as determined by drag coefficient in shock-compressed state. This effect is entirely equivalent to problems associated with elastic moduli determination using ultra… more
Date: June 1, 1993
Creator: Johnson, J. N.; Hixson, R. S.; Tonks, D. L. & Gray, G. T., III
Partner: UNT Libraries Government Documents Department
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Shock experiments in metals and ceramics

Description: Shock recovery and spallation experiments, in which material structure/property effects are systematically varied and characterized quantitatively, offer two important experimental techniques to probe the physical mechanisms controlling shock processes and dynamic fracture. This paper highlights the current state of knowledge and principal challenges of the structure/property effects of shock-wave deformation on metals and ceramics. Recent shock-recovery and spallation experimental results on p… more
Date: January 1, 1990
Creator: Gray, G. T., III
Partner: UNT Libraries Government Documents Department
open access

Shock compression and quasielastic release in tantalum

Description: Previous studies of quasielastic release in shock-loaded FCC metals have shown a strong influence of the defect state on the leading edge, or first observable arrival, of release wave, due to large density of pinned dislocation segments behind the shock front, their relatively large pinning separation, and a very short response time as determined by drag coefficient in shock-compressed state. This effect is entirely equivalent to problems associated with elastic moduli determination using ultra… more
Date: January 1, 1993
Creator: Johnson, J. N.; Hixson, R. S.; Tonks, D. L. & Gray, G. T., III
Partner: UNT Libraries Government Documents Department
open access

A computational study of projectile shape dependence on phase change phenomena with comparisons to experimental data

Description: To make an estimate of the current state of predictive capabilities of hydrocodes for impacts where phase changes may be important, we have simulated a series of experiments where a zinc sphere, rod, and plate impact thin zinc plates at 5 km/s. The experimental data consists of radiographs of the debris cloud and visual evidence of the damage in an aluminum witness plate. CTH was used to simulate the three experiments noted above. A detailed comparison of the simulated debris structure and subs… more
Date: October 1, 1994
Creator: Hertel, E. S., Jr.; McIntosh, R. L. & Patterson, B. C.
Partner: UNT Libraries Government Documents Department
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High strain rate properties and constitutive modeling of glass

Description: This paper presents experimental data and computational modeling for a well-defined glass material. The experimental data cover a wide range of strains, strain rates, and pressures that are obtained from quasi-static compression and tension tests, split Hopkinson pressure bar compression tests, explosively driven flyer plate impact tests, and depth of penetration ballistic tests. The test data are used to obtain constitutive model constants for the improved Johnson-Holmquist (JH-2) brittle mate… more
Date: March 1, 1995
Creator: Holmquist, T. J.; Johnson, G. R.; Lopatin, C. M.; Grady, D. E. & Hertel, E. S., Jr.
Partner: UNT Libraries Government Documents Department
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Reactor Materials Program: Mechanical properties of irradiated Types 304 and 304L stainless steel weldment components

Description: The vessels (reactor tanks) of the Savannah River Site nuclear production reactors constructed in the 1950`s are comprised of Type 304 stainless steel with Type 308 stainless steel weld filler. Irradiation exposure to the reactor tank sidewalls through reactor operation has caused a change in the mechanical properties of these materials. A database of as-irradiated mechanical properties for site-specific materials and irradiation conditions has been produced for reactor tank structural analyses… more
Date: December 1, 1991
Creator: Sindelar, R. L. & Caskey, G. R., Jr.
Partner: UNT Libraries Government Documents Department
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Mechanical properties of 1950`s vintage 304 stainless steel weldment components after low temperature neutron irradiation

Description: The reactor vessels of the nuclear production reactors at the Savannah River Site (SRS) were constructed in the 1950`s from Type 304 stainless steel plates welded with Type 308 stainless steel filler using the multipass metal inert gas process. An irradiated mechanical properties database has been developed for the vessel with materials from archival primary coolant system piping irradiated at low temperatures (75 to 150{degrees}C) in the State University of New York at Buffalo reactor (UBR) an… more
Date: December 31, 1991
Creator: Sindelar, R. L.; Caskey, G. R., Jr.; Thomas, J. K.; Hawthorne, J. R.; Hiser, A. L.; Lott, R. A. et al.
Partner: UNT Libraries Government Documents Department
open access

Mechanical properties of 1950's vintage 304 stainless steel weldment components after low temperature neutron irradiation

Description: The reactor vessels of the nuclear production reactors at the Savannah River Site (SRS) were constructed in the 1950's from Type 304 stainless steel plates welded with Type 308 stainless steel filler using the multipass metal inert gas process. An irradiated mechanical properties database has been developed for the vessel with materials from archival primary coolant system piping irradiated at low temperatures (75 to 150{degrees}C) in the State University of New York at Buffalo reactor (UBR) an… more
Date: January 1, 1991
Creator: Sindelar, R. L.; Caskey, G. R., Jr.; Thomas, J. K. (Westinghouse Savannah River Co., Aiken, SC (United States)); Hawthorne, J. R.; Hiser, A. L. (Materials Engineering Associates, Inc., Lanham, MD (United States)); Lott, R. A. et al.
Partner: UNT Libraries Government Documents Department
open access

Orientation dependency of mechanical properties of 1950`s vintage Type 304 stainless steel weldment components before and after low temperature neutron irradiation

Description: Databases of mechanical properties for both the piping and reactor vessels at the Savannah River Site (SRS) were developed from weldment components (base, weld, and weld heat-affected-zone (HAZ)) of archival piping specimens in the unirradiated and irradiated conditions. Tensile, Charpy V-notch (CVN), and Compact Tension C(T) specimens were tested at 25 and 125C before and after irradiation at low temperatures (90 to 150C) to levels of 0.065 to 2.1 dpa. irradiation hardened the weldment compone… more
Date: December 31, 1992
Creator: Sindelar, R. L. & Caskey, G. R., Jr.
Partner: UNT Libraries Government Documents Department
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Potential for radiation damage to carbon steel storage tanks for high level radioactive waste

Description: A low intensity radiation field is generated by the high level waste that is stored within carbon steel lined tanks at the Savannah River Site (SRS). The highest level of radiation damage to the tank walls from gamma and spontaneous neutron emissions is estimated to be less than 1.0E-6 displacements per atom (DPA) for a 100 year exposure to fresh, ``high heat`` SRS waste assuming continuous replenishment of the radionuclides. This damage level is below the limit for measurable radiation damage … more
Date: July 30, 1993
Creator: Caskey, G. R., Jr.; Sindelar, R. L. & Thomas, J. K.
Partner: UNT Libraries Government Documents Department
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Mechanistic modeling of high-temperature ordered intermetallics

Description: Bulk and defect properties and their relationships with mechanical behavior of transition-metal aluminides and silicides are reviewed on the basis of the recent progress in theoretical modeling studies. For Ti{sub 3}Al, the structural energy difference between the Ll{sub 2} and D0{sub 19} structures was found to be very small, which suggests the possibility of improving ductility through structural modification by ternary additions. While the driving force for the yield strength anomaly in Ni{s… more
Date: July 1995
Creator: Yoo, M. H. & Fu, C. L.
Partner: UNT Libraries Government Documents Department
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