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Development of 400- to 450-MHz RFQ resonator-cavity mechanical designs

Description: In the development of the radio-frequency quadrupole (RFQ) linac, the resonator cavity's mechanical design may be a challenge similar in magnitude to that of the development of the accelerator structure itself. Experience with the all-copper 425-MHz RFQ proof-of-principle linac has demonstrated that the resonator cavity must be structurally stiff and easily tunable. This experience has led to development of copper-plated steel structures having vanes that may be moved within a cylinder for tuni… more
Date: January 1, 1982
Creator: Hansborough, L.D.
Partner: UNT Libraries Government Documents Department
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Joining of ceramics for high performance energy systems. Mid-term progress report, August 1, 1979-March 31, 1980

Description: The subject program is primarily an exploratory and demonstration study of the use of silicate glass-based adhesives for bonding silicon-base refractory ceramics (SiC, Si/sub 3/N/sub 4/). The projected application is 1250 to 2050/sup 0/F relaxing joint service in high-performance energy conversion systems. The five program tasks and their current status are as follows. Task 1 - Long-Term Joint Stability. Time-temperature-transformation studies of candidate glass adhesives, out to 2000 hours sim… more
Date: October 6, 1980
Creator: Smeltzer, C E & Metcalfe, A G
Partner: UNT Libraries Government Documents Department
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Field radiography using 100 Ci of Co-60 without interrupting adjacent manufacturing operations

Description: Radiography is the primary method of Nondestructive Examination recognized by the ASME B and PV Code as providing objective evidence of volumetric examination of the pressure boundary welds that are present in the Clinch River Breeder Reactor Program (CRBRP) Steam Generator. In order to support the steam generator production schedule, the radiographic examinations must be performed without interrupting any other manufacturing or inspection operations taking place within a 20-ft radius from the … more
Date: January 1, 1979
Creator: Donnelly, C.W.
Partner: UNT Libraries Government Documents Department
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Investigation of joining techniques for advanced austenitic alloys

Description: Modified Alloys 316 and 800H, designed for high temperature service, have been developed at Oak Ridge National Laboratory. Assessment of the weldability of the advanced austenitic alloys has been conducted at the University of Tennessee. Four aspects of weldability of the advanced austenitic alloys were included in the investigation.
Date: May 1, 1991
Creator: Lundin, C. D.; Qiao, C. Y. P.; Kikuchi, Y.; Shi, C. & Gill, T. P. S.
Partner: UNT Libraries Government Documents Department
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EXPERIMENTAL INVESTIGATION OF THE EFFECTS OF ULTRASONIC VIBRATIONS ON BURNOUT HEAT FLUX WITH BOILING WATER. Quarterly Technical Progress Report No. 3, April-June 1961

Description: The heat-transfer loop was completed and is in operation. Difficulty was experienced in obtaining a sufficiently strong connection between the burnout- detector voltage tap and the heating element. This problem and its potential solution are described. The lack of means of obtaining controlled burnout prevented collection of data on the burnout effects of the ultrasonic field. (auth)
Date: October 31, 1962
Creator: Romie, F.E.
Partner: UNT Libraries Government Documents Department
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Evaluation of weldments in Type 21-6-9 stainless steel for Compact Ignition Tokamak structural applications: Phase 1

Description: Primary design considerations for the Compact Ignition Tokamak toroidal field-coil cases are yield strength and toughness in the temperature range from 77 to 300 K. Type 21-6-9 stainless steel, also still known by its original Armco Steel Company trade name Nitronic 40, is the proposed alloy for this application. It has high yield strength and usually adequate base metal toughness, but weldments in thick sections have not been adequately characterized in terms of mechanical properties or hot-cr… more
Date: June 1, 1991
Creator: Alexander, D. J.; Goodwin, G. M. & Bloom, E. E.
Partner: UNT Libraries Government Documents Department
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Solder fatigue reduction in point focus photovoltaic concentrator modules

Description: Solder fatigue tests have been conducted on point focus photovoltaic concentration cell assemblies to identify a baseline fatigue life and to quantify the fatigue life improvements that result using a copper-molybdenum-copper low-expansion insert between the solar cell and copper heat spreader. Solder microstructural changes and fatigue crack growth were identified using cross sections and ultrasonic scans of the fatigue solder joints. The Coffin-Manson and Total Strain fatigue models for low-c… more
Date: January 1, 1991
Creator: Hund, T. D. & Burchett, S. N.
Partner: UNT Libraries Government Documents Department
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Effect of high aspect ratio on ITER maintenance design

Description: The International Thermonuclear Experimental Reactor (ITER) baseline machine configuration and auxiliary systems design specify maintainability and repairability as fundamental requirements. Two important maintenance requirements for ITER are a device that is fully remotely maintainable, with the provision for hands-on maintenance wherever possible, and the ability to maintain components with short lives or high failure rates without moving other components or disturbing the machine's internal … more
Date: January 1, 1991
Creator: Herrick, T.J.; Davis, F.C.; Hollis, M.J. & Lousteau, D.C.
Partner: UNT Libraries Government Documents Department
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Effect of Au on the reliability of fine pitch surface mount solder joints

Description: The effect of Au on the reliability of 0.65 mm pitch surface mount solder joints between plastic quad flat packs and Cu-Ni-Au FR-4 printed circuit boards was investigated. Cu-Ni-Au is a desirable printed circuit board finish for multi-chip modules or printed circuit boards that would otherwise require a selective Au finish, for example for edge connectors or wire bondable parts. However, Au is known to embrittle solder when it is present in sufficiently high concentrations, creating a concern t… more
Date: May 1, 1991
Creator: Glazer, J. (Hewlett-Packard Co., Palo Alto, CA (United States)); Kramer, P. & Morris, J.W. Jr. (Lawrence Berkeley Lab., CA (United States))
Partner: UNT Libraries Government Documents Department
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Ultrasonic inspection techniques for two weld closures proposed for RSSF waste storage casks

Description: One method being considered for interim storage of high-level radioactive waste materials is to place these materials in large sealed stainless steel canisters and subsequently store these canisters in a second sealed steel storage cask. Weld procedures are proposed as the closure or seal for these vessels. Inspection of these closures to assure initial and long-term integrity of the closure welds presents a challenge to nondestructive testing. The environment is thermally (400 to 1000/sup 0/F)… more
Date: January 1, 1978
Creator: Doctor, S. R. & Morris, C. J.
Partner: UNT Libraries Government Documents Department
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Microstructural and solidification cracking evaluation of electron beam welds in 304L

Description: Weld hot cracking of stainless steels is a major materials-related problem in the welding industry. This present investigation evaluates the crack susceptibility of highly-constrained EB welds made in materials whose DeLong ferrite potentials range from zero to nine FN. In addition, the effect of piece part strength level on cracking is examined. This study has revealed that these deep penetration EB welds have regions that solidify as primary austenite, even when the DeLong ferrite potential i… more
Date: January 1, 1991
Creator: Sturgill, P.L.; Campbell, R.D. & Henningsen, J.L.
Partner: UNT Libraries Government Documents Department
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Electron-beam fusion welding of beryllium

Description: Ingot-sheet beryllium (Be) having three different chemistries and three different thicknesses was fusion-welded by the electron-beam process. Several different preheats were used to obtain 100% penetration and crack-free welds. Cracking susceptability was found to be related to aluminum (Al) content; the higher Al-content material was most susceptable. However, adequate preheat allowed full penetration and crack-free welds to be made in all materials tested. The effect of a post-weld heat treat… more
Date: January 1, 1978
Creator: Campbell, R. P.; Dixon, R. D. & Liby, A. L.
Partner: UNT Libraries Government Documents Department
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External attachment of titanium sheathed thermocouples to zirconium nuclear fuel rods for the LOFT reactor

Description: The Exxon Nuclear Company, Inc., acting as a Subcontractor to EG and G Idaho Inc., Idaho National Engineering Laboratory, Idaho Falls, Idaho, has developed a welding process to attach titanium sheathed thermocouples to the outside of the zircaloy clad fuel rods. The fuel rods and thermocouples are used to test simulated loss-of-coolant accident (LOCA) conditions in a pressurized water reactor (LOFT Reactor, Idaho National Laboratory). A laser beam was selected as the optimum welding process bec… more
Date: January 1, 1980
Creator: Welty, R.K.
Partner: UNT Libraries Government Documents Department
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Assessment of lamellar tearing

Description: Information on lamellar tearing is summarized and related to proposed ASME Code requirements. Lamellar tearing is characterized as a complex phenomenon related to poor short transverse ductility and through-thickness strain. The material, welding, and design variables that affect lamellar tearing are shown to be complex and interrelated. The commonly reported tests for assessing material susceptibility are described, with the controversy over their validity being carefully detailed. Although th… more
Date: March 1, 1978
Creator: McEnerney, J.W.
Partner: UNT Libraries Government Documents Department
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CRBRP reactor system shield design and impact of new materials irradiation damage data

Description: Structural materials radiation damage data have received considerable attention in the design of LMFBR permanent reactor structures. A recent FFTF/CRBRP structural materials irradiation experiment, conducted as part of the national program plan for irradiation effects on mechanical properties of LMFBR out-of-core structural materials, has found engineering application in setting energy-dependent neutron exposure limits of irradiated structures. This paper describes the impact of the new irradia… more
Date: January 1, 1980
Creator: Wrights, G.N.
Partner: UNT Libraries Government Documents Department
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Acoustic Emission Weld Monitoring of Nuclear Components

Description: Acoustic emission monitoring augments other nondestructive testing methods and is sometimes applicable when other tests cannot be applied. This is, in part, due to the high sensitivity of acoustic emission monitoring. Acoustic emission monitoring is only sensitive to active flaw-growth, however, and will not detect a flaw in equilibrium. This paper describes the application of acoustic emission monitoring to nuclear reactor fuel pin end closure welds and other weldments of the reactor piping.
Date: January 25, 1972
Creator: Romrell, D. M.
Partner: UNT Libraries Government Documents Department
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Evaluation of Inservice Inspection Examinatiions

Description: In order to evaluate the effectiveness of Section 11, Division 1, Rules for Inservice Inspection of Nuclear Power Plant Components,'' of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code examinations, 26 inservice inspection (ISI) summary reports from 24 facilities were reviewed. It was found that these ASME Code examinations and tests are instrumental in revealing indications and defects in welds and plant components. In addition, this study uncovered that fac… more
Date: May 1990
Creator: Aldrich, D. A. & Cook, J. F.
Partner: UNT Libraries Government Documents Department
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Three-dimensional temperature history of a multipass filled weldment. Part 2. [HEATINGS]

Description: Computer simulation of the three-dimensional temperature history in a multipass filled weldment was attempted by modifying a transient heat transfer code, HEATING5. The model includes temperature-dependent physical parameters, radiation and convection heat losses, turbulent and laminar convection in the molten pool, and variable arc velocity, intensity, and weld geometry. The model requires approximately 28 CPU min to simulate one second of welding. 15 figures, 8 tables.
Date: December 21, 1976
Creator: Pinkowish, J.A. & Whitman, P.K.
Partner: UNT Libraries Government Documents Department
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Measured residual stresses in overlay pipe weldments removed from service

Description: Surface and throughwall residual stresses were measured on an elbow-to-pipe weldment that had been removed from the Hatch-2 reactor about a year after the application of a weld overlay. The results were compared with experimental measurements on three mock-up weldments and with finite-element calculations. The comparison shows that there are significant differences in the form and magnitude of the residual stress distributions. However, even after more than a year of service, the residual stres… more
Date: February 1, 1985
Creator: Shack, W.J.
Partner: UNT Libraries Government Documents Department
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Spatial averaging algorithms for ultrasonic inspection of austenitic stainless steel welds

Description: Interpretation of ultrasonic inspection data from stainless steel welds is difficult because the signal-to-noise ratio is very low. The three main reasons for this are the granular structure of the weld, the high attenuation of stainless steel, and electronic noise. Averaging in time at the same position in space reduces electronic noise, but does not reduce ultrasonic noise from grain boundary scattering. Averaging wave-forms from different spatial positions helps reduce grain noise, but desir… more
Date: April 7, 1980
Creator: Horn, J. E.; Cooper, C.S. & Michaels, T.E.
Partner: UNT Libraries Government Documents Department
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Probability of pipe fracture in the primary coolant loop of a PWR plant. Volume 9. PRAISE computer code user's manual. Load Combination Program Project I final report

Description: The PRAISE (Piping Reliability Analysis Including Seismic Events) computer code estimates the influence of earthquakes on the probability of failure at a weld joint in the primary coolant system of a pressurized water reactor. Failure, either a through-wall defect (leak) or a complete pipe severance (a large-LOCA), is assumed to be caused by fatigue crack growth of an as-fabricated interior surface circumferential defect. These defects are assumed to be two-dimensional and semi-elliptical in sh… more
Date: June 1, 1981
Creator: Lim, E.Y.
Partner: UNT Libraries Government Documents Department
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Development of an improved extruded dielectric cable rated 230 kV

Description: Work performed on developing an improved 230 kV extruded solid dielectric cable, the techniques of jointing such cables and the testing of terminations suitable for operation at that voltage level are described. Difficulties were encountered during manufacture in applying the semi-conducting extruded conductor shield. A new higher melt point compound solved the problem. A joint capable of operating at the 230 kV level was developed but showed a deficiency under voltage impulse testing while the… more
Date: May 1, 1977
Creator: Blais, L D; Traut, R T & Bolden, G N
Partner: UNT Libraries Government Documents Department
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Milliwatt generator heat source. Progress report, July-December 1981

Description: As part of the Milliwatt Generator (MWG) Program, a second series of pressure burst capsules welded offsite was tested; the resulting data indicate that the welds are very similar to those in the first series of capsules. Sufficient hardware was fabricated to meet all scheduled commitments. To provide a unit for feasibility testing, a heat source clad with Hastelloy C was reclad with Inconel 600. Forming development tests on Inconel 600 were conducted with favorable results. A QAS-3 survey was … more
Date: April 8, 1982
Creator: Mershad, E.A.
Partner: UNT Libraries Government Documents Department
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WSRC Reactor Tank Inspection Program (RTIP) status report

Description: Westinghouse Savannah River Company (WSRC) recently completed the initial phase of nondestructive inspections of the Savannah River Site's (SRS) reactor tanks. This program required almost three years to be conceptualized, fabricated, and tested. An additional 20 months were required to complete the NDE inspection of the P, K and L reactor tanks. The overall cost of the program to date is approximately $25 MM. This status report will address: (1) A brief review of the RTIP program and the const… more
Date: January 1, 1992
Creator: Loibl, M. W.
Partner: UNT Libraries Government Documents Department
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