[PDF] The Effect Of Cold Rolling On The Susceptibility Of Austenitic Stainless Steel To Stress Corrosion Cracking In Primary Circuit Pressurised Water Reactor Environment eBook

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The Effect of Cold Rolling on the Susceptibility of Austenitic Stainless Steel to Stress Corrosion Cracking in Primary Circuit Pressurised Water Reactor Environment

Author : David Marc Wright
Publisher :
Page : pages
File Size : 48,98 MB
Release : 2012
Category :
ISBN :

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The stress corrosion cracking (SCC) of components which are fabricated from austenitic stainless steel has been observed in the primary circuit of pressurised water reactors (PWR). In recent years it has become an increasing concern that cold work can induce susceptibility to SCC in these materials, even when exposed to good-quality flowing coolant. Laboratory studies which were launched in response to this observation have confirmed that SCC susceptibility is enhanced by cold work. The intention of this study is therefore to investigate the link between the effects of cold work on the material and the susceptibility to SCC. The investigation has been conducted on a grade 304 austenitic stainless steel. Characterisation of the microstructure and mechanical properties has been carried out in the annealed condition, and following cold rolling to a reduction in thickness of 20 %. The cold rolled material has then been subjected to SCC tests in simulated PWR primary circuit coolant. Two types of test were utilised: slow strain rate tests (SSRTs) were carried out in order to investigate the initiation of cracks from a smooth surface and constant load tests using pre-cracked specimens were used to investigate the crack propagation behaviour. In both types of test the SCC produced was predominantly intergranular. The SSRTs revealed that the most susceptible grain boundaries separated grains which had dissimilar deformation microstructures (one grain deformed heavily by planar bands, the other more homogenously). It was also observed that initiation could occur on a grain boundary which is adjacent to an annealing twin. In both microstructural configurations the susceptibility is likely to be due to the deformation incompatibility across the failed boundary, possible indicating that shear at the boundary is important for the initiation of cracking. The crack propagation behaviour of the rolled material was particularly anisotropic; regardless of the loading direction (specimens were manufactured to allow loading along the rolling, transverse and normal plate directions) cracking was observed to occur parallel to the rolling-transverse plane. The origin of this behaviour was explored in terms of preferential alignment of the deformation microstructure and the anisotropic mechanical properties of the rolled plate. Limited transgranular cracking was also observed, which occurred along oxidised deformation bands. The results overall indicate that heterogeneous deformation between different regions of the material, and preferential alignment of the deformation microstructure are important with respect to the SCC susceptibility of the rolled material.

Prediction of Environmental and Strain-rate Effects on the Stress Corrosion Cracking of Austenitic Stainless Steels

Author :
Publisher :
Page : pages
File Size : 31,12 MB
Release : 1985
Category :
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The stress corrosion cracking (SCC) susceptibility of austenitic stainless steels in high-temperature water is controlled by environmental variables (e.g., dissolved oxygen, corrosion potential, impurities), microstructure (e.g., degree of sensitization), and strain rate. A phenomenological model based on the slip-dissolution mechanism and elastic-plastic fracture mechanics is presented to quantitatively describe the effects of both environment-related parameters and strain rate on SCC in constant extension rate tests. The model predictions are in good agreement with the results of tests performed on Types 304, 316, and 316NG stainless steel at different strain rates in a wide variety of environments relevant to boiling-water reactors.

Effects of Water Chemistry on Itergranular Cracking of Irradiated Austenitic Stainless Steels

Author :
Publisher :
Page : 12 pages
File Size : 32,36 MB
Release : 1995
Category :
ISBN :

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To determine the effects of water chemistry on the susceptibility to irradiation-assisted stress corrosion cracking (IASCC) in austenitic stainless steels. constant-extension-rate tests were conducted in simulated BWR environments on several heats of high- and commercial-purity (HP and CP) Type 304 SS specimens from BWR components irradiated to fluences up to 2.4 x 1021 n cm−2 (E> I MeV). Effects of dissolved oxygen (DO) and electrochemical potential (ECP) in 289°C water were investigated. Dependence of Susceptibility to intergranular stress corrosion cracking (IGSCC) on DO was somewhat different for the two materials. Susceptibility of the HP heats. less influenced by DO and ECP, was higher than that of CP material for all DO and fluence levels. Percent IGSCC in the CP material was negligible for DO

Metals Abstracts

Author :
Publisher :
Page : 1342 pages
File Size : 24,85 MB
Release : 1990
Category : Metallurgy
ISBN :

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Stress Corrosion Cracking

Author : V S Raja
Publisher : Elsevier
Page : 817 pages
File Size : 35,62 MB
Release : 2011-09-22
Category : Technology & Engineering
ISBN : 0857093762

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The problem of stress corrosion cracking (SCC), which causes sudden failure of metals and other materials subjected to stress in corrosive environment(s), has a significant impact on a number of sectors including the oil and gas industries and nuclear power production. Stress corrosion cracking reviews the fundamentals of the phenomenon as well as examining stress corrosion behaviour in specific materials and particular industries. The book is divided into four parts. Part one covers the mechanisms of SCC and hydrogen embrittlement, while the focus of part two is on methods of testing for SCC in metals. Chapters in part three each review the phenomenon with reference to a specific material, with a variety of metals, alloys and composites discussed, including steels, titanium alloys and polymer composites. In part four, the effect of SCC in various industries is examined, with chapters covering subjects such as aerospace engineering, nuclear reactors, utilities and pipelines. With its distinguished editors and international team of contributors, Stress corrosion cracking is an essential reference for engineers and designers working with metals, alloys and polymers, and will be an invaluable tool for any industries in which metallic components are exposed to tension, corrosive environments at ambient and high temperatures. Examines the mechanisms of stress corrosion cracking (SCC) presenting recognising testing methods and materials resistant to SCC Assesses the effect of SCC on particular metals featuring steel, stainless steel, nickel-based alloys, magnesium alloys, copper-based alloys and welds in steels Reviews the monitoring and management of SCC and the affect of SCC in different industries such as petrochemical and aerospace

The Effect of Hardening Source in Proton Irradiation-Assisted Stress Corrosion Cracking of Cold Worked Type 304 Stainless Steel

Author : GS. Was
Publisher :
Page : 14 pages
File Size : 22,38 MB
Release : 2004
Category : Austenitic stainless steel
ISBN :

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The goal of this study is to discern whether the irradiation-assisted stress corrosion cracking (IASCC) susceptibility depends on the source of hardening rather than hardening alone. A set of five hardened conditions of commercial 304SS were studied in which the level of hardening remained fixed while the contributions from irradiation and cold work (CW) varied. The extremes of this set were hardening by either proton irradiation at 1.67 dpa only or 35% cold work only. Between these extremes the same value of hardness was reached with a combination of cold work and irradiation. Cold work/proton irradiation combinations used to achieve the target level of hardness were 10% CW + 0.55 dpa, 20% CW + 0.25 dpa, and 25% CW + 0.09 dpa. Proton irradiation was conducted with 3.2 MeV protons at 360°C at a rate of 7 x 10-6 dpa/s. The specimens were then subjected to stress corrosion cracking (SCC) tests in 288°C water typical of normal water chemistry in boiling water reactor (BWR) service conditions. Only the 0% CW + 1.67 dpa and the 10% CW + 0.55 dpa samples showed any sign of IASCC as manifested by intergranular (IG) cracking despite all of the specimens being at the same hardness. All other samples failed without any evidence of IG cracking. Results from this study suggest that radiation hardening, in contrast to cold work, has the most pronounced effect on IASCC.

Review of Environmental Effects on Fatigue Crack Growth of Austenitic Stainless Steels

Author :
Publisher :
Page : pages
File Size : 37,54 MB
Release : 1994
Category :
ISBN :

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Fatigue and environmentally assisted cracking of piping, pressure vessel cladding, and core components in light water reactors are potential concerns to the nuclear industry and regulatory agencies. The degradation processes include intergranular stress corrosion cracking of austenitic stainless steel (SS) piping in boiling water reactors (BWRs), and propagation of fatigue or stress corrosion cracks (which initiate in sensitized SS cladding) into low-alloy ferritic steels in BWR pressure vessels. Crack growth data for wrought and cast austenitic SSs in simulated BWR water, developed at Argonne National Laboratory under US Nuclear Regulatory Commission sponsorship over the past 10 years, have been compiled into a data base along with similar data obtained from the open literature. The data were analyzed to develop corrosion-fatigue curves for austenitic SSs in aqueous environments corresponding to normal BWR water chemistries, for BWRs that add hydrogen to the feedwater, and for pressurized water reactor primary-system-coolant chemistry. The corrosion-fatigue data and curves in water were compared with the air line in Section XI of the ASME Code.