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Localized corrosion of steels in geothermal steam/brine mixtures

Description: Coupons of eight different carbon and chrome-moly alloy steels were exposed to high temperature, high salinity wellhead brine flow at a geothermal well in the Salton Sea Geothermal Field for periods of up to six months. The corrosion rate and corrosion attack morphology of each coupon was determined. Exposure time was a test variable and ranged from one month to six months. Test results indicate that carbon steels generally suffer high corrosion rates and are susceptible to severe localized att… more
Date: May 29, 1980
Creator: McCright, R. D.; Frey, W. F. & Tardiff, G. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Damage analysis and fundamental studies. Quarterly progress report, January-March 1980

Description: The DAFS program element is a national effort composed of contributions from a number of National Laboratories and other government laboratories, universities, and industrial laboratories. It was organized by the Materials and Radiation Effects Branch, Office of Fusion Energy, DOE, and a Task Group on Damage Analysis and Fundamental Studies which operates under the auspices of that Branch. The purpose of this series of reports is to provide a working technical record of that effort for the use … more
Date: May 1, 1980
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Phenomenological model for stress corrosion cracking of Types 316NG and 316 stainless steel. [BWR]

Description: A phenomenological model for both intergranular and transgranular stress corrosion cracking (SCC) in constant extension rate (CERT) tests is discussed. The model is based on an estimate of crack-tip strain rate obtained by use of a J-integral approach, a slip dissolution model for SCC, and a J-integral fracture criterion. The model is used to derive correlations between the SCC parameters (such as time to failure and average crack growth rate) and applied (nominal) strain rate. The model is ext… more
Date: May 1, 1985
Creator: Maiya, P.S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Materials erosion and redeposition studies at the PISCES-facility: net erosion under redeposition

Description: Simultaneous erosion and redeposition of copper and 304 stainless steel under controlled and continuous plasma (D,He,Ar) bombardment has been investigated in the PISCES-facility, which generates typical edge-plasma conditions of magnetic fusion devices. The plasma bombardment conditions are: incident ion flux in the range from 10/sup 17/ to 10/sup 18/ ions/sec/cm/sup 2/, ion bombarding energy of 100 eV, electron temperature in the range from 5 to 15 eV, plasma density in the range from 10/sup 1… more
Date: May 1, 1986
Creator: Hirooka, Y.; Goebel, D. M.; Conn, R. W.; Leung, W. K. & Campbell, G. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Microstructural Stability and Oxidation Resistance of 9-12 Chromium Steels at Elevated Temperatures

Description: Various martensitic 9-12 Cr steels are utilized currently in fossil fuel powered energy plants for their good elevated temperature properties such as creep strength, steam side oxidation resistance, fire side corrosion resistance, and thermal fatigue resistance. Need for further improvements on the properties of 9-12 Cr steels for higher temperature (>600oC) use is driven by the environmental concerns (i.e., improve efficiency to reduce emissions and fossil fuel consumption). In this paper, we … more
Date: May 1, 2006
Creator: Dogan, O. N.; Alman, D. E.; Jablonski, P. D. & Hawk, J. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Applications of simultaneous ion backscattering and ion-induced x-ray emission

Description: Simultaneous ion backscattering and ion-induced x-ray emission (E/sub x/greater than or equal to 300 eV) analyses have been performed using helium ions as probes of the first few hundred nanometers of various materials. These studies serve as a demonstration of the complementary nature of the two types of information obtained. Uncertainties associated with each of the individual techniques were reduced by performing both analyses. The principal advantages of simultaneous analyses over sequentia… more
Date: May 1, 1983
Creator: Musket, R.G.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Material options for a commercial fusion reactor first wall

Description: A study has been conducted to evaluate the potential of various materials for use as first walls in high-power-density commercial fusion reactors. Operating limits for each material were obtained based on a number of criteria, including maximum allowable structural temperatures, critical heat flux, ultimate tensile strength, and design-allowable stress. The results with water as a coolant indicate that a modified alloy similar to HT-9 may be a suitable candidate for low- and medium-power-densit… more
Date: May 1, 1986
Creator: Dabiri, A. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effects of tensile and compressive stresses on irradiation-induced swelling in AISI 316. [LMFBR]

Description: The results of two recent experiments indicate that the current perception of stress-affected swelling needs revision. It appears that compressive stresses do not delay swelling as previously modeled but actually accelerate swelling at a rate comparable to that induced by tensile stresses.
Date: May 1, 1985
Creator: Lauritzen, T.; Bell, W. L.; Konze, G. M.; Rosa, J. M.; Vaidyanathan, S. & Garner, F. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Microstructural comparison of HT-9 irradiated in HFIR and EBR-II

Description: A series of specimens of HT-9 heat 91354 have been examined following irradiation in HFIR to 39 dpa at 300, 400, 500 and 600/sup 0/C and following irradiation in EBR-II to 29 dpa at 390 and 500/sup 0/C. HFIR irradiation was found to have promoted helium bubble formation at all temperatures and voids at 400/sup 0/C. Cavitation had not been observed at lower fluence, nor was it found in EBR-II irradiated specimens. The onset of void swelling in HFIR is attributed to helium generation. The observa… more
Date: May 1, 1985
Creator: Gelles, D. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Assessment of the performance potential of the martensitic alloy HT-9 for liquid-metal fast-breeder-reactor applications

Description: Martensitic stainless steels appear to provide attractive alternatives to austenitic stainless steels for liquid metal fast breeder reactors (LMFBR). The United States National Cladding/Duct (NCD) Materials Development Program has selected Sandvik alloy HT-9 (12CrMoW) as one of six prime candidate alloys for advanced in-core structural materials having very high peak burnup capabilities. The NCD program, since 1974, has been accumulating engineering data for HT-9. Properties include swelling, i… more
Date: May 1, 1983
Creator: Straalsund, J. L. & Gelles, D. S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Fossil energy program. Progress report, March 1979

Description: This report - the fifty-sixth of a series - is a compendium of monthly progress reports for the ORNL research and development programs that are in support of the increased utilization of coal and other fossil fuel alternatives to oil and gas as sources of clean energy. The projects reported this month include those for coal conversion development, materials engineering, a coal equipment test program, an atmospheric fluid bed combustor for cogeneration, engineering studies and technical support,… more
Date: May 1, 1979
Creator: McNeese, L.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fossil Energy Program progress report for April 1979

Description: This report - the fifty-seventh of a series - is a compendium of monthly progress reports for the ORNL research and development programs that are in support of the increased utilization of coal and other fossil fuel alternatives to oil and gas as sources of clean energy. The projects reported this month include those for coal conversion progress development, chemical research and development, materials engineering, a coal equipment test program, engineering studies and technical support, proces… more
Date: May 1, 1979
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Develop of the climb induced glide concept to describee in-reactor creep of FCC materials

Description: The Climb Induced Glide model (CIG) for irradiation creep is developed using a plastic flow law which has been successfully applied in the correlation of Type 316 stainless steel rupture data. This model is used to predict the stress and temperature dependence of irradiation creep and the transition from irradiation to thermal creep. The predictions of this model are compared and found to be qualitatively consistent with experimental data and microstructural information. This model allows predi… more
Date: May 1, 1979
Creator: Chin, B. A.; Straalsund, J. L. & Gilbert, E. R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Precipitation hardening in Fe--Ni base austenitic alloys

Description: The precipitation of metastable Ni/sub 3/X phases in the austenitic Fe--Ni-base alloys has been investigated by using various combinations of hardening elements, including Ti, Ta, Al, and Nb. The theoretical background on the formation of transition precipitates has been summarized based on: atomic size, compressibility, and electron/atom ratio. A model is proposed from an analysis of static concentration waves ordering the fcc lattice. Ordered structure of metastable precipitates will change f… more
Date: May 1, 1979
Creator: Chang, K.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Mixed oxide fuel development

Description: This paper describes the success of the ongoing mixed-oxide fuel development program in the United States aimed at qualifying an economical fuel system for liquid metal cooled reactors. This development has been the cornerstone of the US program for the past 20 years and has proceeded in a deliberate and highly disciplined fashion with high emphasis on fuel reliability and operational safety as major features of an economical fuel system. The program progresses from feature testing in EBR-II to… more
Date: May 8, 1987
Creator: Leggett, R. D. & Omberg, R. P.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Behavior of Type 316 stainless steel under simulated fusion reactor irradiation

Description: Fusion reactor irradiation response in alloys containing nickel can be simulated in thermal-spectrum fission reactors, where displacement damage is produced by the high-energy neutrons and helium is produced by the capture of two thermal neutrons in the reactions: /sup 58/Ni + n ..-->.. /sup 59/Ni + ..gamma..; /sup 59/Ni + n ..-->.. /sup 56/Fe + ..cap alpha... Examination of type 316 stainless steel specimens irradiated in HFIR has shown that swelling due to cavity formation and degradati… more
Date: May 1, 1978
Creator: Wiffen, F. W.; Maziasz, P. J.; Bloom, E. E.; Stiegler, J. O. & Grossbeck, M. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Study of Deformation and Fatigue of 316 Stainless Steel at Room Temperature by Positron Annihilation

Description: Scoping studies have been initiated to evaluate the potential of positron annihilation as a volumetric nondestructive examination technique. The first experiments have shown that positron annihilation provides a sensitive monitor of plastic deformation caused by cold rolling and of fatigue cycling of 316 stainless steel at room temperature. Transmission electron microscopy examination of the fatigued samples has shown a direct relationship between dislocation density and the positron annihilati… more
Date: May 1, 1978
Creator: Gauster, W. B.; Wampler, W. R.; Jones, W. B. & Van den Avyle, J. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of laser welding techniques for hydrogen transmission. Progress report, April 1, 1978--April 30, 1978

Description: Machining of the A106B GTA and EB welded specimens was completed. Laser welding of the AISI 304L and ASTM A106B materials is continuing. Tensile testing of the ASTM A106B EB welded specimens was initiated and completed. Testing of the ASTM A106B EB welded material indicated generally lower ductility than the parent material. Low-cycle fatigue testing of the ASTM A106B material in 13.8 MPa hydrogen indicates reductions in mean life of approximately 50 and 27% due to the GTA and EB welding respec… more
Date: May 19, 1978
Creator: Mucci, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Steam explosion triggering phenomena: stainless steel and corium-E simulants studied with a floodable arc melting apparatus. [BWR; PWR]

Description: Laboratory-scale experiments on the thermal interaction of light water reactor core materials with water have been performed. Samples (10--35 g) of Type 304 stainless steel and Corium-E simulants were each flooded with approximately 1.5 litres of water to determine whether steam explosions would occur naturally. Many of the experiments also employed artificially induced pressure transients in an attempt to initiate steam explosions. Vigorous interactions were not observed when the triggering pu… more
Date: May 1, 1978
Creator: Nelson, L. S. & Buxton, L. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of laser welding techniques for hydrogen transmission. Final report, September 1977-November 1979

Description: This program was established to determine the feasibility of laser beam welding as a fabrication method for hydrogen transmission and is a precursor in the effort to systematically provide the technological base necessary for large-scale, economic pipeline transmission of fuel for a hydrogen energy system. The study contributes to the technology base by establishing the effect of conventional weld processes and laser beam welding on the mechanical properties of two classes of steels in an air a… more
Date: May 1, 1980
Creator: Mucci, J
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Microstructure of low energy deuterium implanted stainless steel

Description: Transmission electron microscopy has been used to determine the defect structure produced in stainless steel by deuterium ions of energies from 0.3 to 5 keV. These energies are typical of neutral atoms incident on the first wall of current tokamak devices. At room temperature, high defect densities were found at our lowest dose of 1 x 10/sup 15/ D/sup +//cm/sup 2/. With increasing dose, the defect structures coarsened, and lattice strain effects in the implanted region became noticeable. Follow… more
Date: May 1, 1978
Creator: Thomas, G. J. & Wilson, K. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Corrosion of several metals in supercritical steam at 538/sup 0/C. [85 alloys]

Description: The corrosion of several iron- and nickel-base alloys in supercritical steam at 24.1 MPa (3500 psi) and 538/sup 0/C was measured to 7.92 x 10/sup 7/ s (22,000 h). The experiments were carried out in TVA's Bull Run Steam Plant. Corrosion was measured almost entirely by weight change and visual appearance; a few samples were evaluated by more descriptive analytical techniques. The corrosion rates of low-alloy ferritic steels containing from 1.1 to 8.7 percent Cr and 0.5 to 1.0 percent Mo dif… more
Date: May 1, 1977
Creator: McCoy, H. E. & McNabb, B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactor safety research programs. Quarterly progress report, January 1--March 31, 1977

Description: The projects reported each quarter are the following: Gas Reactor Safety Evaluation, THOR Code Development, SSC Code Development, LMFBR and LWR Safety Experiments, Fast Reactor Safety Code Validation, Technical Coordination of Structural Integrity, and Fast Reactor Safety Reliability Assessment.
Date: May 1, 1977
Creator: Romano, A. J. (comp.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Joining uranium to steel

Description: A method has been devised which will allow the joining of uranium to steel by fusion welding through the use of an intermediate material. Uranium-0.5 titanium was joined to AISI 304L stainless steel by using a vanadium insert. Also, a method is now available for selecting possible filler metals when two entirely dissimilar metals need to be joined. This method allows a quantitative ranking to be made of the possible filler metals and thus the most likely candidate can be selected.
Date: May 1, 1976
Creator: Perkins, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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