Literature Survey - Stress Corrosion Cracking of Alloy 600 Steam Generator Tubing PDF Download

Author: Keith Matuszyk
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Category :
Languages : en
Pages : 55

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Languages : en
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A single heat of Inconel Alloy 600 was examined in this work, using slow strain rate tests (SSRT) in simulated primary water at temperatures of 325°−345sup 0/-365°C. The best measure of stress corrosion cracking (SCC) was percent SCC present on the fracture surface. Strain rate did not seem to affect crack growth rate significantly, but there is some question about the accuracy of calculating these values in the absence of a direct indication of when a crack initiates. Demarcation was determined between domains of temperature/strain rate where SCC either did, or did not, occur. Slower extension rates were needed to produce SCC as the temperature was lowered. 10 figs.

Author: GP. Airey
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ISBN:
Category : Alloys
Languages : en
Pages : 20

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The stress-corrosion cracking (SCC) resistance of commercially fabricated mill-annealed and thermally treated Inconel Alloy 600 steam generator tubing was evaluated over a range of sodium hydroxide concentrations (10 to 50 percent), test temperatures [316 to 343 °C (600 to 650 °F)] and applied stresses (50 to 150 percent yield stress). The grain boundary microstructure was compared with that previously observed in laboratory-treated material. The SCC resistance of thermally treated tubing was superior to that of the mill-annealed product for all test conditions. It was confirmed that the improvement in caustic SCC resistance correlated with the presence of a semicontinuous grain-boundary chromium carbide precipitate. Grain boundary segregation (phosphorus, boron) and chromium depletion do not adversely affect SCC performance. The presence of copper oxide reduced SCC resistance, whereas the presence of silica inhibited SCC. These observations were rationalized by reference to the anodic polarization curve.

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Languages : en
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The most recent corrosion problems experienced in nuclear steam generators tubed with Inconel alloy 600 is a phenomenon labeled ''denting''. Denting has been found in various degrees of severity in many operating pressurized water reactors. Laboratory investigations have shown that Inconel 600 exhibits intergranular SCC when subjected to high stresses and exposed to deoxygenated water at elevated temperatures. A research project was initiated at Brookhaven National Laboratory in an attempt to improve the qualitative and quantitative understanding of factors influencing SCC in high temperature service-related environments. An effort is also being made to develop an accelerated test method which could be used to predict the service life of tubes which have been deformed or are actively denting. Several heats of commercial Inconel 600 tubing were procured for testing in deaerated pure and primary water at temperatures from 290 to 365/sup 0/C. U-bend type specimens were used to determine crack initiation times which may be expected for tubes where denting has occurred but is arrested and provide baseline data for judging the accelerating effects of the slow strain rate method. Constant extension rate tests were employed to determine the crack velocities experienced in the crack propagation stage and predict failure times of tubes which are actively denting. 8 refs., 17 figs., 5 tabs.

Author: Bruce William Brisson
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ISBN:
Category :
Languages : en
Pages : 294

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Alloy 600, the material used for pressurized water reactor steam generator tubing, is susceptible to environmentally assisted stress corrosion cracking. Intergranular stress corrosion cracking (IGSCC) attacks the tubes in areas of high residual stress, and in crevice regions. No method has been successfully developed to monitor steam generator tubing in-situ for crack initiation and growth. Essentially all available published IGSCC crack growth data for alloy 600 is based on non-tubing material. Although it is very likely that the current data base is applicable to tubing processing, differences between tube and other geometries make a comparison between tubing and other data important for verification purposes. However, obtaining crack initiation and growth data from tubing is difficult due to the geometry and the thin wall thickness.

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Languages : en
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Results of stress-corrosion cracking data are presented for Inconel 600 steam-generator tubing. U-bend, constant-load, and slow extension-rate tests are included. Arrhenius plots are presented for failure times vs inverse temperature for crack initiation and propagation. Effect of applied load is expressed in terms of log-log curves for failure times vs stress, and variations in environment and cold work are included. Microstructure and composition of oxide films on Inconel 600 surfaces were examined after exposure to pure water at 365°C, and stripping with the bromine-methanol method. Results are discussed in terms of transient creep, film rupture and a mass-transport-limited anodic process.

Author: T. S. Bulischeck
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Category : Inconel
Languages : en
Pages : 56

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Author: Electricité de France. Direction des études et recherches
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Category :
Languages : en
Pages : 25

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Author: I. J. Muir
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Category :
Languages : en
Pages : 0

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Author: G. Goszczynski
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Category :
Languages : en
Pages : 0

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