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Effects of temperature and radiation on the nuclear waste glass product consistency leach test

Description: Previous leach studies carried out with monolithic glass samples have shown that glass dissolution rates increase with increasing temperature and may or may not increase on exposure to external gamma radiolysis. In this study we have investigated the effects of temperature (70--1200[degrees]C) and radiation on the dissolution of simulated radioactive waste glasses using the Product Consistency Test (PCT). The PCT is a seven day, crushed glass leach test in deionized water that is carried out at… more
Date: January 1, 1993
Creator: Crawford, C.L. & Bibler, N.E.
Partner: UNT Libraries Government Documents Department
open access

Corrosion fatigue of iron-chromium-nickel alloys: Fracture mechanics, microstructure and chemistry

Description: Phase transformation and cracking during RT aging of charged, high-purity Fe18Cr12Ni alloy and commerical 304 ss were examined; results show that [epsilon]* (hcp) hydride formed on Fe18Cr12Ni upon charging, and it decomposed rapidly to form first [epsilon] and then [alpha]' martensite. Morphology of fracture surfaces of Fe18Cr12Ni produced by corrosion fatigue in NaCl solutions and in hydrogen was found to be identical. Effort was made to examine the approaches and methodologies used in service… more
Date: January 25, 1993
Creator: Wei, R.P.
Partner: UNT Libraries Government Documents Department
open access

Potential high fluence response of pressure vessel internals constructed from austenitic stainless steels

Description: Many of the in-core components in pressurized water reactors are constructed of austenitic stainless steels. The potential behavior of these components can be predicted using data on similar steels irradiated at much higher displacement rates in liquid-metal reactors or water-cooled mixed-spectrum reactors. Consideration of the differences between the pressurized water environment and that of the other reactors leads to the conclusion that significant amounts of void swelling, irradiation creep… more
Date: August 1, 1993
Creator: Garner, F. A.; Greenwood, L. R. & Harrod, D. L.
Partner: UNT Libraries Government Documents Department
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Grain boundary chromium concentration effects on the IGSCC and IASCC of austenitic stainless steels

Description: Comparisons are made between grain boundary composition and intergranular stress corrosion cracking (IGSCC) of 304 and 309 austenitic stainless steels in high-temperature water environments. Chromium depletion had the dominant effect on cracking resistance with the extent of IG cracking controlled by the interfacial chromium concentration. The minimum chromium concentration required to promote cracking was a function of the applied strain rate during slow-strain-rate tensile tests in 288 C air-… more
Date: August 1, 1993
Creator: Bruemmer, S. M.; Arey, B. W. & Charlot, L. A.
Partner: UNT Libraries Government Documents Department
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Thermomechanical history measurements on Type 304L stainless steel pipe girth welds

Description: Thermal and strain histories were recorded for three 40-cm-diameter (16 inch), Type 304L stainless steel (SS), schedule 40 (1.27 cm thickness) pipe girth welds. Two weld groove preparations were standard V grooves while the third was a narrow groove configuration. The welding parameters for the three pipe welds simulated expected field practice as closely as possible. The narrow gap weld was completed in four continuous passes while the other two welds required six and nine (discontinuous) pass… more
Date: December 31, 1993
Creator: Li, Ming; Atteridge, D. G.; Anderson, W. E.; Turpin, R. & West, S. L.
Partner: UNT Libraries Government Documents Department
open access

Effect of vibratory stress relief during welding of thick stainless steel plate

Description: Residual strains were measured in two welded 25-mm thick plates of type 304 stainless steel by the neutron diffraction technique. The filler metal employed to weld these plates was type 308 stainless steel. One of the two welds was prepared without any vibratory stress relief treatment and the other was vibrated at a frequency below the resonant condition which gives a fraction the resonant amplitude during welding. In both plates the largest residual stress component found in the heat affected… more
Date: December 31, 1993
Creator: Spooner, S.; David, S. A.; Wang, X. L.; Hubbard, C. R.; Holden, T. M. & Root, J. H.
Partner: UNT Libraries Government Documents Department
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Low temperature hydrothermal processing of organic contaminants in Hanford tank waste

Description: Batch and continuous flow reactor tests at Pacific Northwest Laboratory (PNL) have shown that organics similar to those present in the single-shell and double-shell underground storage tanks at Hanford can be decomposed in the liquid phase at relatively mild temperatures of 150{degree}C to 350{degree}C in an aqueous process known as hydrothermal processing (HTP). The organics will react with the abundant oxidants such s nitrite already present in the Hanford tank waste to form hydrogen, carbon … more
Date: February 1, 1993
Creator: Jones, E. O.; Pederson, L. R.; Freeman, H. D.; Schmidt, A. J. & Babad, H.
Partner: UNT Libraries Government Documents Department
open access

Effects of temperature and radiation on the nuclear waste glass product consistency leach test

Description: Previous leach studies carried out with monolithic glass samples have shown that glass dissolution rates increase with increasing temperature and may or may not increase on exposure to external gamma radiolysis. In this study we have investigated the effects of temperature (70--1200{degrees}C) and radiation on the dissolution of simulated radioactive waste glasses using the Product Consistency Test (PCT). The PCT is a seven day, crushed glass leach test in deionized water that is carried out at… more
Date: April 1, 1993
Creator: Crawford, C. L. & Bibler, N. E.
Partner: UNT Libraries Government Documents Department
open access

Hanford high-level waste evaporator/crystallizer corrosion evaluation

Description: The US Department of Energy, Hanford Site nuclear reservation, located in Southeastern Washington State, is currently home to 61 Mgal of radioactive waste stored in 177 large underground storage tanks. As an intermediate waste volume reduction, the 242-A Evaporator/Crystallizer processes waste solutions from most of the operating laboratories and plants on the Hanford Site. The waste solutions are concentrated in the Evaporator/Crystallizer to a slurry of liquid and crystallized salts. This con… more
Date: October 1, 1993
Creator: Ohl, P. C. & Carlos, W. C.
Partner: UNT Libraries Government Documents Department
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Foil support structure for large electron guns

Description: This paper describes a novel support structure for a vacuum diode used to pump a gaseous laser with an electron beam. Conventional support structures are designed to hold a foil flat and rigid. This new structure takes advantage of the significantly greater strength of metals in pure tension, utilizing curved shapes for both foil and support structure. The shape of the foil is comparable to the skin of a balloon, and the shape of the support structures is comparable to the cables of a suspensio… more
Date: August 1, 1993
Creator: Brucker, J. P. & Rose, E. A.
Partner: UNT Libraries Government Documents Department
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Inelastic analysis acceptance criteria for radioactive material transportation containers

Description: The design criteria currently used in the design of radioactive material (RAM) transportation containers are taken from the ASME Boiler and Pressure Vessel Code (ASME, 1992). These load-based criteria are ideally suited for pressure vessels where the loading is quasistatic and all stresses are in equilibrium with externally applied loads. For impact events, the use of load-based criteria is less supportable. Impact events tend to be energy controlled, and thus, energy-based acceptance criteria … more
Date: June 1, 1993
Creator: Ammerman, D. J. & Ludwigsen, J. S.
Partner: UNT Libraries Government Documents Department
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Effect of internal heating during hot compression testing on the stress-strain behavior and hot working characteristics of Alloy 304L

Description: Temperature change from conversion of deformation to internal heat, and its effect on stress-strain behavior of alloy 304L was investigated by initially isothermal (temperature of specimen, compression dies, environment equilibrated at initiation of test) uniaxial compression. Strain rate was varied 0.01 s{sup {minus}1} to 1 s{sup {minus}1} (thermal state of specimen varied from nearly isothermal to nearly adiabatic). Specimens were deformed at 750 to 1150 to a strain of 1. Change in temperatur… more
Date: May 1, 1993
Creator: Mataya, M. C. & Sackschewsky, V. E.
Partner: UNT Libraries Government Documents Department
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Welding irradiated stainless steel

Description: Conventional welding processes produced severe underbead cracking in irradiated stainless steel containing 1 to 33 appm helium from n,a reactions. A shallow penetration overlay technique was successfully demonstrated for welding irradiated stainless steel. The technique was applied to irradiated 304 stainless steel that contained 10 appm helium. Surface cracking, present in conventional welds made on the same steel at the same and lower helium concentrations, was eliminated. Underbead cracking … more
Date: December 31, 1993
Creator: Kanne, W. R., Jr.; Chandler, G. T.; Nelson, D. Z. & Franco-Ferreira, E. A.
Partner: UNT Libraries Government Documents Department
open access

Reactor Materials Program -- weldment component toughness of SRS PWS piping materials. Task number: 89-023-1

Description: The mechanical properties of austenitic stainless steel materials from the reactor systems in the unirradiated (baseline) and the irradiated conditions have been developed previously for structural and fracture analyses of the pressure boundary of the SRS reactor Process Water System (PWS) components. Individual mechanical specimen test results were compiled into three separate weldment components or regions, namely, the base, weld, and weld heat-affected-zone (HAZ), for two orientations (L-C a… more
Date: February 1, 1993
Creator: Sindelar, R. L.
Partner: UNT Libraries Government Documents Department
open access

Cutting and drilling studies using high power visible lasers

Description: High power and radiance laser technologies developed at Lawrence Livermore National Laboratory such as copper-vapor and dye lasers show great promise for material processing tasks. Evaluation of models suggests significant increases in welding, cutting, and drilling capabilities, as well as applications in emerging technologies such as micromachining, surface treatment, and stereolithography. Copper lasers currently operate at 1.8 kW output at approximately three times the diffraction limit and… more
Date: May 27, 1993
Creator: Kautz, D. D.; Dragon, E. P.; Werve, M. E.; Hargrove, R. S. & Warner, B. E.
Partner: UNT Libraries Government Documents Department
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Laser materials processing applications at Lawrence Livermore National Laboratory

Description: High power and high radiance laser technologies developed at Lawrence Livermore National Laboratory (LLNL) such as copper-vapor lasers, solid-state slab lasers, dye lasers, harmonic wavelength conversion of these lasers, and fiber optic delivery systems show great promise for material processing tasks. Evaluation of models suggests significant potential for tenfold increases in welding, cutting, and drilling performance, as well as capability for applications in emerging technologies such as mi… more
Date: February 25, 1993
Creator: Hargrove, R. S.; Dragon, E. P.; Hackel, R. P.; Kautz, D. D. & Warner, B. E.
Partner: UNT Libraries Government Documents Department
open access

Corrosion fatigue of iron-chromium-nickel alloys: Fracture mechanics, microstructure and chemistry. Progress report, January 1, 1992--December 31, 1992

Description: Phase transformation and cracking during RT aging of charged, high-purity Fe18Cr12Ni alloy and commerical 304 ss were examined; results show that {epsilon}* (hcp) hydride formed on Fe18Cr12Ni upon charging, and it decomposed rapidly to form first {epsilon} and then {alpha}` martensite. Morphology of fracture surfaces of Fe18Cr12Ni produced by corrosion fatigue in NaCl solutions and in hydrogen was found to be identical. Effort was made to examine the approaches and methodologies used in service… more
Date: January 25, 1993
Creator: Wei, R. P.
Partner: UNT Libraries Government Documents Department
open access

Summary of work on coatings and claddings for fossil energy applications

Description: A summary of efforts to examine coatings and cladding materials for high-strength austenitic steels is provided. Chromized coatings on 17--14CuMo stainless steel and a modified type 316 (HT-UPS) stainless steel were investigated. Claddings included alloy 671, 690, and an iron-aluminide intermetallic alloy. Structural alloys that were clad included type 304 stainless steel, modified type 316 stainless steel, and modified alloy 800H. The capability of producing co-extruded tubing of the experimen… more
Date: May 1, 1993
Creator: Swindeman, R. W.
Partner: UNT Libraries Government Documents Department
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Overlay welding irradiated stainless steel

Description: An overlay technique developed for welding irradiated stainless steel may be important for repair or modification of fusion reactor materials. Helium, present due to n,{alpha} reactions, is known to cause cracking using conventional welding methods. Stainless steel impregnated with 3 to 220 appm helium by decay of tritium was used to develop a welding process that could be used for repair. The result was a gas metal arc weld overlay technique with low-heat input and low-penetration into the hel… more
Date: August 1, 1993
Creator: Kanne, W. R., Jr.; Chandler, G. T.; Nelson, D. Z. & Franco-Ferreira, E. A.
Partner: UNT Libraries Government Documents Department
open access

Reactor Materials Program -- weldment component toughness of SRS PWS piping materials. [Process Water System]

Description: The mechanical properties of austenitic stainless steel materials from the reactor systems in the unirradiated (baseline) and the irradiated conditions have been developed previously for structural and fracture analyses of the pressure boundary of the SRS reactor Process Water System (PWS) components. Individual mechanical specimen test results were compiled into three separate weldment components or regions, namely, the base, weld, and weld heat-affected-zone (HAZ), for two orientations (L-C a… more
Date: February 1, 1993
Creator: Sindelar, R. L.
Partner: UNT Libraries Government Documents Department
open access

Defect-solute interactions near irradiation grain boundaries

Description: Defect-solute interactions control radiation-induced segregation (RIS) to interfacial sinks, such as grain boundaries, in metallic materials. The best studied system in this regard has been austenitic stainless steels. Measurements of grain boundary composition indicate that RIS of major alloying elements are in reasonable agreement with inverse-Kirkendall predictions. The steep and narrow composition profiles are shown to result from limited back diffusion near the boundary. Subsequently, defe… more
Date: November 1, 1993
Creator: Simonen, E. P.; Vetrano, J. S.; Heinisch, H. L. & Bruemmer, S. M.
Partner: UNT Libraries Government Documents Department
open access

Vapor deposition of copper on stainless steel 304L

Description: Y-12 Plant is seeking to minimize the generation of hazardous wastes in its operations. The standard procedure for electroplating a thin layer of copper on type 304L stainless steel requires several aqueous pretreatment steps which generate Resource Conservation and Recovery Act (RCRA) hazardous wastes. We have evaluated a more environmentally acceptable procedure. Copper was vacuum deposited onto 304L coupons under differing deposition conditions and properties of coatings produced, including … more
Date: August 17, 1993
Creator: Vasofsky, R. W.
Partner: UNT Libraries Government Documents Department
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Analysis of crack initiation and growth in the high level vibration test at Tadotsu

Description: The High Level Vibration Test data are used to assess the accuracy and usefulness of current engineering methodologies for predicting crack initiation and growth in a cast stainless steel pipe elbow under complex, large amplitude loading. The data were obtained by testing at room temperature a large scale modified model of one loop of a PWR primary coolant system at the Tadotsu Engineering Laboratory in Japan. Fatigue crack initiation time is reasonably predicted by applying a modified local st… more
Date: August 1, 1993
Creator: Kassir, M. K.; Park, Y. J.; Hofmayer, C. H.; Bandyopadhyay, K. K. & Shteyngart, S.
Partner: UNT Libraries Government Documents Department
open access

Transmission Electron Microscopy Study of Thick Copper-304 Stainless Steel Multilayers

Description: Thick (10 to 25 {mu}m), free-standing, equal layer thickness, Copper(Cu)-304 Stainless Steel(SS) multilayer foils, having periods of 1 to 100 nm, synthesized by magnetron sputter deposition, were examined by plan view and cross-sectional transmission electron microscopy. Multilayer growth morphology, individual layer structure and crystallographic phase orientation relationships were characterized in this study. Electron Energy Loss filtered imaging of a 20 nm period multilayer cross-section wa… more
Date: June 8, 1993
Creator: Wall, M. A.; Barbee, T. W., Jr. & Weihs, T.
Partner: UNT Libraries Government Documents Department
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