Author: I. J. MuirPublisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Sims and metallographic examination of stress-corrosion cracks in alloy 600 steam-generator tubing. part ii : primary-water stress-corrosion cracks in a tube section from ringhals-2
Author: I. J. MuirSims and metallographic examination of stress-corrosion cracks in alloy 600 steam-generator tubing. part i : secondary-side cracks in tube sections from ringhals-2 and tihange-1
Author: S. J. BushbyNinth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems
Author: Steve BruemmerPublisher: John Wiley & Sons
ISBN: 1118787773
Category : Technology & Engineering
Languages : en
Pages : 1776
Book Description
This collection presents an exchange of ideas among scientists and engineers about the economic and safety concerns surrounding environmentally induced materials problems which lead to nuclear power plant outages. Scientists and engineers concerned with the environmental degradation processes (corrosion, mechanical, and radiation effects) present their latest results on such topics as life extension/relicensing and materials problems associated with spent fuel storage and radioactive waste disposal. This collection will be of interest to utility engineers, reactor vendor engineers, plant architect engineers, researchers concerned with materials degradation, and consultants involved in design, construction, and operation of water reactors.
Literature Survey - Stress Corrosion Cracking of Alloy 600 Steam Generator Tubing
Author: Keith MatuszykStrain Rate and Temperature Effects on the Stress Corrosion Cracking of Inconel 600 Steam Generator Tubing in the Primary Water Conditions
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
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.
Stress Corrosion Crack Detection in Alloy 600 in High Temperature Caustic
Author: Bruce William BrissonPublisher:
ISBN:
Category :
Languages : en
Pages : 294
Book Description
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.
Corrosion Evaluation of Thermally Treated Alloy 600 Tubing in Primary and Faulted Secondary Water Environments
Author: Stress Corrosion Cracking of Alloy 600 Using the Constant Strain Rate Test
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
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.
Primary Water Stress Corrosion Cracking of Alloy 600
Author: Publisher:
ISBN:
Category :
Languages : en
Pages : 13
Book Description
Correlations of stress corrosion cracking (SCC) data in deaerated water with temperature, stress, metallography, and processing for laboratory test specimens are presented. Initiation time data show that a low temperature anneal and resulting absence of grain boundary carbides result in a material having increased susceptibility to SCC. Data also show that hot worked and annealed Alloy 600 is more resistant than cold worked and annealed material, both having carbide decorated grain boundaries. In absence of grain boundary carbides, both materials are equally susceptible. Low temperature thermal treatment (1100F) reduces SCC susceptibility with or without grain boundary decoration. Weld metal data and data correlations developed from 700 double U-bends are presented. Data demonstrate the effect of increased carbon content to improve SCC resistance. The data shows that the general relation of time, temperature and strain for wrought material is followed for the weld metal. The weld process used did not affect the SCC susceptibility of EN-82 which showed a greater resistance to SCC than EN-62. Stress relief of weld deposits showed an improvement for wrought material. Heat affected zone resistance was improved if the starting material received a high temperature anneal (1850 to 2000F). Range of SCC initiation times for weld metal is comparable to the range of initiation times for wrought material.
A Caustic Stress-Corrosion Cracking Evaluation of Thermally Treated Inconel Alloy 600 Steam Generator Tubing
Author: GP. AireyPublisher:
ISBN:
Category : Alloys
Languages : en
Pages : 20
Book Description
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.