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In context of acceptability of 17-4 PH in sour service, an literature survey of complex metallurgy of this grade was done following a mechanical rupture in service. In addition, three 17-4 PH materials were studied in terms of microstructure, mechanical properties and susceptibility to sulfide stress cracking.
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The intent was to understand if the low ferrite limits commonly associated with acceptable toughness in austenitic welds can be used on ASTM A 351 Grade CF3M and CF8M castings.
This paper describes a novel methodology to measure the Critical Pitting Temperature (CPT) of a Duplex Stainless Steels (DSS) in artificial seawater based on the Electrochemical Noise (ECN) technique.
Stainless steel UNS S17400 (17-4PH) has been successfully used in oilfield services outside the traditional NACE MR0175/ISO 15156 limits for permanent equipment. The exact operational envelops of 17-4PH (HH1150), including the tensile threshold stress, sour gas partial pressure, temperature, and exposure time that enable the crack-free usage of 17-4PH (HH1150) are not well established. For service equipment, NACE MR0175/ISO15156 currently provides exemptions from the tight environmental restrictions of permanent equipment, but instead limits the maximum applied stress to a debatable 60% of the specified minimum yield strength (SMYS). In this investigation, the sulfide stress-corrosion cracking of 17-4PH is revisited through 51 new NACE TM0177 Methods A tests conducted over 240 hours minimum (480hrs in certain cases). Under unrestricted sour gas partial pressures, the threshold tensile stress below which cracking does not occur is between 45% and 60% of the SMYS at ambient temperature. Alloy 17-4PH is also less susceptible to sulfide stress cracking as temperature increases from 70°F (21°C) to 350°F (177°C). Risk of sulfide stress cracking is also greatly mitigated when delta ferrite is controlled. With reduced delta ferrite, as provided by two out of three tested heats, and reverted austenite promoted by both chemical composition and longer aging treatments, no cracking is seen at 60% stress level up to 45psi H2S (0.31MPa); at 45% stress level, this value is increased to 120psi (0.83MPa) based on newly-collected test data.
Austenitic stainless steels (AuSS) are widely used as structural materials for nuclear reactor vessel internals (RVIs), as well as for fuel cladding and pressurizer components. Some of these components cannot be removed and replaced, and therefore the irradiation performance of the steel determines the lifetime of each reactor component. Typical irradiation-induced detrimental effects in light water-cooled power reactors include embrittlement, accelerated creep, and radiation-altered corrosion. Some second-order effects such as void swelling, hydrogen accumulation, and radiation-induced phase instability might be slowly evolving to first-order importance, especially as Western nuclear power plants are being considered for lifetime extensions to 60 and possibly 80 total years.