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in subjects: "Incoloy Alloys"

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Effect of fission product interactions on the corrosion and mechanical properties of HTGR alloys. [HTGR]

Preliminary experiments have been carried out to determine how fission product interactions may influence the mechanical integrity of reference HTGR structural metals. In this work Type 304 stainless steel, Incoloy 800 and Hastelloy X were heated to 550 to 650/sup 0/C in the presence of CsI. It was found that no corrosion of the alloys occurred unless air or oxygen was also present. A mechanism for the observed behavior is proposed. A description is also given of some long term exposures of HTG… more

Date: January 1, 1978

Creator: Aronson, S.; Chow, J.G.Y.; Soo, P. & Friedlander, M.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Tritium permeability of structural materials and surface effects on permeation rates

Tritium management in any system always will include containment such that tritium release rates will be less than established limits and also will be as low as practical. The well known properties of hydrogen to permeate through most materials make the complete containment of tritium an impossible task. However, tritium release rates from a given system can be minimized by two primary efforts. First is the selection of a compatible containment material which frequently also will be the structu… more

Date: January 1, 1980

Creator: Bell, J T; Redman, J D & Bittner, H F

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Tritium permeation through Incoloy 800 oxidized in situ by water vapor

The in situ formation of oxide layers on the surfaces of heat exchangers in the steam system of a fusion power plant may be the most feasible way to control tritium release into the steam. Tritium permeabilities of Incoloy 800 have been determined while the downstream surface was oxidized by water vapor at 525, 660 and 720/sup 0/C. The in situ formation of oxide coatings on the Incoloy 800 surface has been observed to reduce tritium permeabilities by factors of 30 to 700 depending on conditions… more

Date: January 1, 1978

Creator: Bell, J T; Redman, J D; Bittner, H F & Christie, W H

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Progress toward analytical description of the creep strain-time behavior of engineering alloys

Elevated-temperature design methods in the United States often require a comprehensive description of the properties of the construction materials. These descriptions include representations for creep strain-time behavior as a function of stress, temperature, and material variability. Work conducted at this laboratory in the past five years toward the development of analytical techniques to derive such representations is summarized. Results for several common elevated-temperature structural mat… more

Date: January 1, 1980

Creator: Booker, M. K.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Use of generalized regression models for the analysis of stress-rupture data

The design of components for operation in an elevated-temperature environment often requires a detailed consideration of the creep and creep-rupture properties of the construction materials involved. Techniques for the analysis and extrapolation of creep data have been widely discussed. The paper presents a generalized regression approach to the analysis of such data. This approach has been applied to multiple heat data sets for types 304 and 316 austenitic stainless steel, ferritic 2/sup 1///s… more

Date: January 1, 1978

Creator: Booker, M. K.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Study of tertiary creep instability in several elevated-temperature structural materials

Data for a number of common elevated temperature structural materials have been analyzed to yield mathematical predictions for the time and strain to tertiary creep at various rupture lives and temperatures. Materials examined include types 304 and 316 stainless steel, 2 1/4 Cr-1 Mo steel, alloy 800H, alloy 718, Hastelloy alloy X, and ERNiCr--3 weld metal. Data were typically examined over a range of creep temperatures for rupture lives ranging from less than 100 to greater than 10,000 hours. W… more

Date: January 1, 1978

Creator: Booker, M. K. & Sikka, V. K.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

High-level waste canister corrosion studies pertinent to geologic isolation

The compatibility of candidate high-level waste (HLW) canister materials with deep geologic isolation environments is addressed. Results are presented which are applicable to the following repositories or test facilities: bedded and domed salt, sub-seabed sediment, and various types of hardrock. Such studies are an essential portion of the technological basis for terminal waste management. These studies will identify HLW canister or overpack materials satisfying appropriate requirements for bar… more

Date: December 1, 1978

Creator: Braithwaite, J.W. & Molecke, M.A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Creep-fatigue effects in structural materials used in advanced nuclear power generating systems

Various aspects of time-dependent fatigue behavior of a number of structural alloys in use or planned for use in advanced nuclear power generating systems are reviewed. Materials included are types 304 and 316 stainless steel, Fe-2 1/4 Cr-1 Mo steel, and alloy 800H. Examples of environmental effects, including both chemical and physical interaction, are presented for a number of environments. The environments discussed are high-purity liquid sodium, high vacuum, air, impure helium, and irradiat… more

Date: January 1, 1980

Creator: Brinkman, C.R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Overview of U. S. efforts directed towards development of mechanical properties data in support of FBR development

The object of U.S. Breeder Reactor Program associated with primary and secondary circuit structural materials is to develop a design data base and associated design technology on commercially available material as well as new alloys. The commercially available materials include ASIA 316 and 304. Chromium--molybdenum steels and alloy 800H. (FS)

Date: January 1, 1978

Creator: Brinkman, C.R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Molten nitrate salt technology development status report

Recognizing thermal energy storage as potentially critical to the successful commercialization of solar thermal power systems, the Department of Energy (DOE) has established a comprehensive and aggressive thermal energy storage technology development program. Of the fluids proposed for heat transfer and energy storage molten nitrate salts offer significant economic advantages. The nitrate salt of most interest is a binary mixture of NaNO/sub 3/ and KNO/sub 3/. Although nitrate/nitrite mixtures … more

Date: March 1981

Creator: Carling, R. W.; Kramer, C. M.; Bradshaw, R. W.; Nissen, D. A.; Goods, S. H.; Mar, R. W. et al.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Steam generator materials performance in high temperature gas-cooled reactors

This paper reviews the materials technology aspects of steam generators for HTGRs which feature a graphite-moderated, uranium-thorium, all-ceramic core and utilizes high-pressure helium as the primary coolant. The steam generators are exposed to gas-side temperatures approaching 760/sup 0/C and produce superheated steam at 538/sup 0/C and 16.5 MPa (2400 psi). The prototype Peach Bottom I 40-MW(e) HTGR was operated for 1349 EFPD over 7 years. Examination after decommissioning of the U-tube steam… more

Date: November 1, 1980

Creator: Chafey, J. E. & Roberts, D. I.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

High-temperature gas-cooled reactor safety studies. Progress report for January 1, 1974--June 30, 1975

Progress is reported in the following areas: systems and safety analysis; fission product technology; primary coolant technology; seismic and vibration technology; confinement components; primary system materials technology; safety instrumentation; loss of flow accident analysis using HEATUP code; use of coupled-conduction-convection model for core thermal analysis; development of multichannel conduction-convection program HEXEREI; cooling system performance after shutdown; core auxiliary cooli… more

Date: July 1, 1977

Creator: Cole, T. E.; Sanders, J. P. & Kasten, P. R.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Basalt Waste Isolation Project. Quarterly report, January 1-March 31, 1980

This report addresses the technical progress for the Basalt Waste Isolation Project for the second quarter of fiscal year 1980. Seismic design values were developed for preliminary repository design purposes; 0.25 g horizontal and 0.125 g vertical maximum accelerations for surface, zero-period conditions. Preliminary seismic data indicate broad, smooth areas exist in the bedrock surface in the western portion of the Cold Creek syncline and a gently undulating bedrock surface in the eastern port… more

Date: April 1, 1980

Creator: Deju, R.A.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Materials technology for coal-conversion processes. Eleventh quarterly report, April--June 1977

Silicon-carbide refractories with various bond systems exposed to molten slag at 1500/sup 0/C for 500 h in Run 4 showed virtually no attack. The resistance of the silicon carbide to slag attack is attributed to large thermal fluxes induced by water-cooled chills applied to the cold faces. Magnesia-chromia refractories exposed to molten slag at 1500/sup 0/C for 500 h in Run 5 were somewhat less resistant to slag attack than the silicon-carbide refractories. In-situ erosive-wear measurements on t… more

Date: January 1, 1977

Creator: Ellingson, W A

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Materials technology for coal-conversion processes. Sixteenth quarterly report, October--December 1978

Refractories for slag containment, nondestructive evaluation methods, corrosion, erosion, and component failures were studied. Analysis of coal slags reveal ferritic contents of 18 to 61%, suggesting a partial pressure of 0/sub 2/ in the slagging zone of approx. 10/sup -2/ to 10/sup -4/ Pa. A second field test of the high-temperature ultrasonic erosion-monitoring system was completed. Ultrasonic inspecton of the HYGAS cyclone separator shows a reduced erosive-wear rate at 5000 h in the stellite… more

Date: January 1, 1978

Creator: Ellingson, W A

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Materials technology for coal-conversion processes. Fifteenth quarterly report, July--September 1978

In the evaluation of ceramic refractories for slagging gasifiers the fused-cast chrome-spinel refractory (number 22) exhibited excellent corrosion resistance at approx. 1550/sup 0/C, even without water cooling. The fused-cast chrome-alumina (number 38) also performed well, whereas the silicon carbide and alumina-silica refractories exhibited substantial corrosion. Field work on ultrasonic erosion-detection systems has continued with data acquisition during a plant run at Bi-Gas. Uniaxial tensil… more

Date: January 1, 1978

Creator: Ellingson, W.A.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Atmospheric fluidized bed combustion technology test unit for industrial cogeneration plants

The AFBC Technology Test Unit Program will develop the technology for a fluidized bed coal combustion system to provide a source of high temperature air for process heating and power generation with gas turbines in industrial plants. The gas turbine has the advantages of a higher ratio of electric power output to exhaust heat load and a higher exhaust temperature than do steam turbines in cogeneration applications. This type of system appears to be attractive for development, particularly for i… more

Date: January 1, 1977

Creator: Fraas, A. P. & Holcomb, R. S.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Heat exchanger materials for fluidized bed coal combustors

The 4500-h test in the FluiDyne AFBC tells us three things: (1) ferritic and austenitic superheater alloys perform well to approximately 590/sup 0/C (1100/sup 0/F), (2) high-temperature alloys can perform well at approximately 870/sup 0/C (1600/sup 0/F), and (3) they also may fail miserably at approximately 870/sup 0/C (1600/sup 0/F). Additional studies are clearly needed to develop a fundamental understanding of corrosion mechanisms in AFBC and to determine the envelope of safe operating condi… more

Date: January 1, 1980

Creator: Godfrey, T. G.; Copper, R. H.; DeVan, J. H. & Drake, K. R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Exposure of high-temperature alloys in carbonaceous gas atmospheres

Light and scanning electron microscopy were used to evaluate changes resulting from exposure of eight commercial high temperature alloys in carbonaceous atmospheres. Samples were exposed in CO, CH$sub 4$, or CO/CH$sub 4$ mixtures up to 900$sup 0$C and 6.2 MPa. All alloys were actively attacked. Surface finish and preoxidation influenced the extent of corrosion. Reduction of NiO, giving a high surface concentration of Ni, promoted catalytic decomposition of CH$sub 4$. Further work is indicated b… more

Date: September 1, 1975

Creator: Goldberg, A. & Perkins, A.J.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Long-term oxidation of selected alloys in superheated steam at 482 and 538/sup 0/C

The oxidation of several Cr-Mo steels and austenitic materials in superheated steam at 482 and 538/sup 0/C (900 and 1000/sup 0/F) is studied. The investigation was conducted in a once-through loop that received steam from the superheater circuit of the Bartow Power Plant of the Florida Power Corporation. This report presents the results from this investigation, which was terminated after 28,339 h when the mode of power plant operation was changed from baseload to peaking.

Date: July 1, 1981

Creator: Griess, J. C. & Maxwell, W. A.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Oxidation of selected alloys during 25,000 h in superheated steam at 482 and 538/sup 0/C

The corrosion of several ferritic and austenitic materials in flowing superheated steam at 482 and 538/sup 0/C (900 and 1000/sup 0/F) were studied. Results obtained during the first 12,000 h of the test were presented previously. Results obtained during the first 25,000 h are summarized. The test specimens are mounted in a nonrecirculating loop that receives steam from the superheater circuit of a fossil-fired power plant. At both temperatures all materials exhibited parabolic oxidation kinetic… more

Date: March 1, 1980

Creator: Griess, J. C. & Maxwell, W. A.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Effect of simulated medium-Btu coal gasifier atmospheres on the biaxial stress rupture behavior of four candidate coal gasifier alloys

Tests were conducted to determine whether the biaxial stress rupture behavior of four alloys was adversely affected by exposure to four simulated medium-Btu coal gasifier atmospheres. The results of exposures up to approximately 500 h at temperatures between 649 and 982/sup 0/C are presented. Exposure to these atmospheres at temperatures below 900/sup 0/C did not significantly reduce the rupture properties from those measured in air. Only at 982/sup 0/C were the rupture strength and life in the… more

Date: January 1, 1982

Creator: Horton, R. M. & Smolik, G. R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Relationship between carburization and zero-applied-stress creep dilation in Alloy 800H and Hastelloy X. [HTGR]

Typical HTGR candidate alloys can carburize when exposed to simulated service environments. The carbon concentration gradients so formed give rise to internal stresses which could cause dilation. Studies performed with Hastelloy X and Alloy 800H showed that dilations of up to almost 1% can occur at 1000/sup 0/C when carbon pickup is high. Dilation was normally observed only when the carbon increase was >1000 ..mu..g/cm/sup 2/ and ceased when the diffusing carbon reached the center of the specim… more

Date: January 1, 1981

Creator: Inouye, H. & Rittenhouse, P.L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Effects of irradiation and thermal aging upon fatigue-crack growth behavior of reactor pressure boundary materials. [Neutrons]

Two processes that have the potential to produce degradation in the properties of pressure boundary materials are neutron irradiation and long-time thermal aging. This paper uses linear-elastic fracture mechanics techniques to assess the effect of these two processes upon the fatigue-crack growth behavior of a number of alloys commonly employed in reactor pressure boundaries. The materials evaluated include ferritic steels, austenitic stainless steels, and nickel-base alloys typical of those em… more

Date: October 1, 1978

Creator: James, L. A.

Item Type: Article

Partner: UNT Libraries Government Documents Department