Academic literature on the topic 'Austenitic stainless steel Cracking'

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Journal articles on the topic "Austenitic stainless steel Cracking"

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Topolska, S., and J. Łabanowski. "Environmental Degradation of Dissimilar Austenitic 316L and Duplex 2205 Stainless Steels Welded Joints." Archives of Metallurgy and Materials 62, no. 4 (December 1, 2017): 2107–12. http://dx.doi.org/10.1515/amm-2017-0312.

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AbstractThe paper describes structure and properties of dissimilar stainless steels welded joints between duplex 2205 and austenitic 316L steels. Investigations were focused on environmentally assisted cracking of welded joints. The susceptibility to stress corrosion cracking (SCC) and hydrogen embrittlement was determined in slow strain rate tests (SSRT) with the strain rate of 2.2 × 10−6s−1. Chloride-inducted SCC was determined in the 35% boiling water solution of MgCl2environment at 125°C. Hydrogen assisted SCC tests were performed in synthetic sea water under cathodic polarization condition. It was shown that place of the lowest resistance to chloride stress corrosion cracking is heat affected zone at duplex steel side of dissimilar joins. That phenomenon was connected with undesirable structure of HAZ comprising of large fractions of ferrite grains with acicular austenite phase. Hydrogen assisted SCC tests showed significant reduction in ductility of duplex 2205 steel while austenitic 316L steel remains almost immune to degradation processes. SSR tests of dissimilar welded joints revealed a fracture in the area of austenitic steel.
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Wang, Wenbin, Li Xiong, Dan Wang, Qin Ma, Yan Hu, Guanzhi Hu, and Yucheng Lei. "A New Test Method for Evaluation of Solidification Cracking Susceptibility of Stainless Steel during Laser Welding." Materials 13, no. 14 (July 16, 2020): 3178. http://dx.doi.org/10.3390/ma13143178.

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A new test method named “Trapezoidal hot” cracking test was developed to evaluate solidification cracking susceptibility of stainless steel during laser welding. The new test method was used to obtain the solidification cracking directly, and the solidification cracking susceptibility could be evaluated by the solidification cracking rate, defined as the ratio of the solidification cracking length to the weld bead length under certain conditions. The results show that with the increase in the solidification cracking rate, the solidification cracking susceptibility of SUS310 stainless steel was much higher than that of SUS316 and SUS304 stainless steels during laser welding (at a welding speed of 1.0 m/min) because a fully austenite structure appeared in the weld joint of the former steel, while the others were ferrite and austenitic mixed structures during solidification. Besides, with an increase in welding speed from 1.0 to 2.0 m/min during laser welding, the solidification cracking susceptibility of SUS310 stainless steel decreased slightly; however, there was a tendency towards an increase in the solidification cracking susceptibility of SUS304 stainless steel due to the decrease in the amount of ferrite under a higher cooling rate.
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Shankar, V., T. P. S. Gill, S. L. Mannan, and S. Sundaresan. "Solidification cracking in austenitic stainless steel welds." Sadhana 28, no. 3-4 (June 2003): 359–82. http://dx.doi.org/10.1007/bf02706438.

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Setargew, Nega, and Daniel J. Parker. "Zinc diffusion induced precipitation of σ-phase in austenitic stainless steel." Metallurgical Research & Technology 116, no. 6 (2019): 618. http://dx.doi.org/10.1051/metal/2019040.

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Zinc diffusion-induced degradation of AISI 316LN austenitic stainless steel pot equipment used in 55%Al-Zn and Zn-Al-Mg coating metal baths is described. SEM/EDS analyses results showed that the diffused zinc reacts with nickel from the austenite matrix and results in the formation of Ni-Zn intermetallic compounds. The Ni-Zn intermetallic phase and the nickel depleted zones form a periodic and alternating layered structure and a mechanism for its formation is proposed. The role of cavities and interconnected porosity in zinc vapour diffusion-induced degradation and formation of Ni-Zn intermediate phases is also discussed. The formation of Ni-Zn intermediate phases and the depletion of nickel in the austenite matrix results in the precipitation of σ-phase and α-ferrite in the nickel depleted regions of the matrix. This reaction will lead to increased susceptibility to intergranular cracking and accelerated corrosion of immersed pot equipment in the coating bath. Zinc diffusion induced precipitation of σ-phase in austenitic stainless steels that we are reporting in this work is a new insight with important implications for the performance of austenitic stainless steels in zinc containing metal coating baths and other process industries. This new insight will further lead to improved understanding of the role of substitutional diffusion and the redistribution of alloying elements in the precipitation of σ-phase in austenitic stainless steels.
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Sundaresan, S. "Metallurgy of Welding Stainless Steels." Advanced Materials Research 794 (September 2013): 274–88. http://dx.doi.org/10.4028/www.scientific.net/amr.794.274.

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Based primarily on microstructure, five stainless steel types are recognized: ferritic, martensitic, austenitic, duplex and precipitation-hardening. The major problem in ferritic stainless steels is the tendency to embrittlement, aggravated by various causes. During welding, control of heat input is essential and, in some cases, also a postweld heat treatment. The austenitic type is the easiest to weld, but two important issues are involved in the welding of these steels: hot cracking and formation of chromium carbide and other secondary phases on thermal exposure. The nature of the problems and remedial measures are discussed from a metallurgical perspective. Duplex stainless steels contain approximately equal proportions of austenite and ferrite. The article discusses the upset in phase balance during welding both in the weld metal and heat-affected zone and the formation of embrittling secondary phases during any thermal treatment. Martensitic stainless steels are susceptible to hydrogen-induced cracking. Welding thus involves many precautions to prevent it through proper preheat selection, postweld heat treatment, etc. In the welding of precipitation-hardening stainless steels, it is usually necessary to develop in the weld metal strength levels matching those of the base metal. This is achieved by applying a postweld heat treatment appropriate to each type of alloy.
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Stradomski, G. "The Cracking Mechanism of Ferritic-Austenitic Cast Steel." Archives of Foundry Engineering 16, no. 4 (December 1, 2016): 153–56. http://dx.doi.org/10.1515/afe-2016-0101.

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Abstract In the high-alloy, ferritic - austenitic (duplex) stainless steels high tendency to cracking, mainly hot-is induced by micro segregation processes and change of crystallization mechanism in its final stage. The article is a continuation of the problems presented in earlier papers [1 - 4]. In the range of high temperature cracking appear one mechanism a decohesion - intergranular however, depending on the chemical composition of the steel, various structural factors decide of the occurrence of hot cracking. The low-carbon and low-alloy cast steel casting hot cracking cause are type II sulphide, in high carbon tool cast steel secondary cementite mesh and / or ledeburite segregated at the grain solidified grains boundaries, in the case of Hadfield steel phosphorus - carbide eutectic, which carrier is iron-manganese and low solubility of phosphorus in high manganese matrix. In duplex cast steel the additional factor increasing the risk of cracking it is very “rich” chemical composition and related with it processes of precipitation of many secondary phases.
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Truschner, Mathias, Jacqueline Deutsch, Gregor Mori, and Andreas Keplinger. "Cathodic and Anodic Stress Corrosion Cracking of a New High-Strength CrNiMnMoN Austenitic Stainless Steel." Metals 10, no. 11 (November 19, 2020): 1541. http://dx.doi.org/10.3390/met10111541.

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A new high-nitrogen austenitic stainless steel with excellent mechanical properties was tested for its resistance to stress corrosion cracking. The new conventional produced hybrid CrNiMnMoN stainless steel combines the excellent mechanical properties of CrMnN stainless steels with the good corrosion properties of CrNiMo stainless steels. Possible applications of such a high-strength material are wires in maritime environments. In principle, the material can come into direct contact with high chloride solutions as well as low pH containing media. The resistance against chloride-induced stress corrosion cracking was determined by slow strain rate tests and constant load tests in different chloride-containing solutions at elevated temperatures. Resistance to hydrogen-induced stress corrosion cracking was investigated by precharging and ongoing in-situ hydrogen charging in both slow strain rate test and constant load test. The hydrogen charging was carried out by cathodic charging in 3.5 wt.% NaCl solution with addition of 1 g/L thiourea as corrosion inhibitor and recombination inhibitor to ensure hydrogen absorption with negligible corrosive attack. Slow strain rate tests only lead to hydrogen induced stress corrosion cracking by in-situ charging, which leads to total hydrogen contents of more than 10 wt.-ppm and not by precharging alone. Excellent resistance to chloride-induced stress corrosion cracking in 43 wt.% CaCl2 at 120 °C and in 5 wt.% NaCl buffered pH 3.5 solution at 80 °C is obtained for the investigated austenitic stainless steel.
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Khoshnaw, Fuad Mohamed, and Hussein Bakir Rahmatalla. "Stress Corrosion Cracking Behaviour of Welded Duplex Stainless Steel." Advanced Materials Research 89-91 (January 2010): 709–14. http://dx.doi.org/10.4028/www.scientific.net/amr.89-91.709.

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This study investigated stress corrosion cracking of two welded stainless steel alloys, austenitic 304L and duplex 2205, in an acidic chloride solution. Different heat inputs are selected for welding the alloys, using tungsten inert gas, with and without filler metal. The slow strain rate technique is utilized to estimate the susceptibility of each weldment to stress corrosion cracking. Different strain rates are used, and the experiments showed that the strain rate equal to 1.66x10-6/sec is a critical value that can be used for assessing the susceptibility of the alloys to corrosion cracking. A numerical index used in this study to evaluate this susceptibility, which is based on a ratio between elongation percent of each alloy in the solution to that in the air. The results showed that the austenitic alloy has higher ductility than duplex in air, while there was not a big difference between both alloys in the solution. Increasing the heat input in autogenous welding caused a brittleness, i.e. less elongation, for both alloys. The results showed that the austenitic alloy is exposed to stress corrosion cracking in the solution, before and after welding, with or without filler metals. On the other hand, the duplex alloy showed higher resistance to stress corrosion cracking than the austenitic alloy due to the high chromium content, and it is dual phase.
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Correia, Maria J., and Manuela M. Salta. "Stress Corrosion Cracking of Austenitic Stainless Steel Alloys for Reinforced Concrete." Materials Science Forum 514-516 (May 2006): 1511–15. http://dx.doi.org/10.4028/www.scientific.net/msf.514-516.1511.

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The corrosion resistance under mechanical stress can be one of the most concerning types of localized corrosion for the application of stainless steel reinforcements in concrete. This paper will assess the stress corrosion cracking susceptibility, by the slow strain rate test method (SSRT), of three austenitic stainless steel alloys: one conventional Fe-Cr-Ni base alloy and two new composition Fe-Cr-Mn base alloys adequate to the manufacturing of ribbed bars for reinforcing concrete. The SSRT results show that only one of the austenitic Fe-Cr-Mn alloys is susceptible to stress corrosion cracking while the other shows a performance similar to that of the AISI 304 stainless steel alloy.
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Prabowo, Harris, Badrul Munir, Yudha Pratesa, and Johny W. Soedarsono. "Comparison of 2507 Duplex and 28 % Cr- Austenitic Stainless Steel Corrosion Behavior for High Pressure and High Temperature (HPHT) in Sour Service Condition with C-ring Experiment." Periodica Polytechnica Mechanical Engineering 65, no. 3 (July 5, 2021): 280–85. http://dx.doi.org/10.3311/ppme.17598.

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The scarcity of oil and gas resources made High Pressure and High Temperature (HPHT) reservoir attractive to be developed. The sour service environment gives an additional factor in material selection for HPHT reservoir. Austenitic 28 Cr and super duplex stainless steel 2507 (SS 2507) are proposed to be a potential materials candidate for such conditions. C-ring tests were performed to investigate their corrosion behavior, specifically sulfide stress cracking (SSC) and sulfide stress cracking susceptibility. The C-ring tests were done under 2.55 % H2S (31.48 psia) and 50 % CO2 (617.25 psia). The testing was done in static environment conditions. Regardless of good SSC resistance for both materials, different pitting resistance is seen in both materials. The pitting resistance did not follow the general Pitting Resistance Equivalent Number (PREN), since SS 2507 super duplex (PREN > 40) has more pitting density than 28 Cr austenitic stainless steel (PREN < 40). SS 2507 super duplex pit shape tends to be larger but shallower than 28 Cr austenitic stainless steel. 28 Cr austenitic stainless steel has a smaller pit density, yet deeper and isolated.
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Dissertations / Theses on the topic "Austenitic stainless steel Cracking"

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Raseroka, Mantsaye S. "Controlled chloride cracking of austenitic stainless steel." Pretoria : [s.n.], 2009. http://upetd.up.ac.za/thesis/available/etd-07032009-120615/.

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Albores-Silva, Octavio E. "Atmospheric stress corrosion cracking and pitting of austenitic stainless steel." Thesis, University of Newcastle Upon Tyne, 2011. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.579513.

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The atmospherically-induced stress corrosion cracking (AISCC) of austenitic stainless steel type AISI 316L was investigated using a U-bend technique, under conditions relevant for storage of intermediate level radioactive waste drums. The specimens were obtained from an actual '500 litre' drum with a wet-bead blasted surface finish. Using MgCI2 as contaminant salt, it was found that at the characteristic equilibrium relative humidity a threshold deposition for AISCC occurrence is found above chloride-ion contamination levels of 10 and 25 µg cm-2 at 50 and 30 °C, respectively. Higher contamination levels were required to produce cracking at room temperature or with the increase of relative humidity to 60 %. The AISCC severity was related to the spatial characteristics of the electrolyte film. Above 100 µg cm-2, crack depth seems to be controlled by the electrolyte thickness as it determines the diffusion path of oxygen to the cathodic surface. Below 100 µg cm-2, crack depth is affected predominantly by the formation of a discontinuous electrolyte film which results in smaller anodic/cathodic domains. Transition from cracking to pitting corrosion with tunnel appearance was observed as test temperature was decreased from 30 °C to room temperature, except at high chloride deposition levels. The results indicate that AISCC occurrence can be limited by restriction of chloride deposition, control of RH away from the deliquescence point of relevant salts and control of temperature. Using an X-ray diffraction technique, it was found that the drum's surface residual stresses are compressive and would provide a degree of protection against AISCC. However, tensile residual stresses can be found in non-blasted areas and in sections of the drum welds. Exposure of corrosion coupons and U-bend specimens III an underground environment that potentially resembles a geological disposal facility did not cause any significant pitting or AISCC after 1.75 years of exposure. This was correlated to a low chloride deposition and a high average RH that would have maintained the hygroscopic deposits in a dilute condition.
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Scatigno, Giuseppe Giovanni. "Chloride-induced transgranular stress corrosion cracking of austenitic stainless steel 304L." Thesis, Imperial College London, 2016. http://hdl.handle.net/10044/1/51506.

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Stress corrosion cracking (SCC) of austenitic stainless steels has been a known failure mode for more than 80 years and it continues to be a major cause of concern in the nuclear industry. The so-called nuclear grades, such as 304L, contain low levels of C and are therefore hard to sensitise, which is a major problem with high C grades, and these low C grades mainly fail by transgranular SCC. The effect of cold work (CW) has long been known to have a detrimental effect on SCC performance of a stainless steel component. CW is readily introduced in engineering components, through manufacturing history, or implementation, i.e. welding and hammering during fitting. The aim of this thesis is to systematically assess the role of CW in Cl-induced atmospheric SCC in 304L grade austenitic stainless steel. 304L is widely used in the nuclear industry, for both the primary cooling system of nuclear power plants and dry casks for interim storage of spent nuclear fuel. CW was applied in uniaxial tension to levels of 0, 0.5, 1, 2, 5 10, 20, and 40%. The specimens were loaded in a jig to produce a uniform stress of 60 MPa on the top surface and corroded under atmospheric conditions at 75°C, 70% relative humidity, using MgCl2, for 20 days. The role of applied stress (from 60-180 MPa), on SCC susceptibility was investigated at a fixed level of CW (chosen as 10% CW after preliminary experiments) using indicators such as crack density. Secondary and transmission electron microscopy, electron back-scattered diffraction, focused ion beam and secondary ion spectroscopy were the main characterisation techniques used. The maximum susceptibility to SCC was observed between 0.5-5% CW, while 20 and 40% CW did not exhibit cracking. The characterisation of the samples tested provided evidence that Cl is found ahead of the crack tip, whereas oxygen is not, which was never previously observed in the literature. Secondary ion mass spectroscopy and transmission electron microscopy were both used to observe and study the presence of Cl. Simulations such as SRIM and Casino 3.2 were used to confirm that the findings were not a technique artefact. Evidence of dealloying was also observed during the characterisation. Dealloying has long been deemed unlikely in Cl-SCC of austenitic stainless steel, but recent work showed that this may also be an available mechanism for SCC as more and more of the characteristics features of dealloying are observed. The dealloying signs observed were: nanoporosity, found on fracture surfaces; severe striations, heavy dissolution of slip planes; element migration (areas of light and dark contrast in back scattered electron images, dictated by the migration of Cr); cleavage failure; Cr and Ni migration around the crack. The role of salt loading was investigated. Different levels of salt deposition were tested in order to obtain an engineering threshold for salt deposition, namely: low ( < 5.70 x 10-3 g cm-2), medium (5.70 x 10-3–1.42 x 10-2 g cm-2) and high ( > 1.42 x 10-2 g cm-2). A linear relationship was observed between level of salt deposited and both crack density and corrosion area. However, more work is necessary to obtain a threshold.
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Sui, Gaoyi. "Some aspects of stress corrosion cracking of Type 316 stainless steel steam generator tubes." Thesis, University of Newcastle Upon Tyne, 1990. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.481644.

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Gulbrandsen, Stephani. "Stress corrosion cracking of 316L austenitic stainless steel in high temperature ethanol/water environments." Thesis, Georgia Institute of Technology, 2012. http://hdl.handle.net/1853/47815.

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There has been an increase in the production of bio-fuels. Organosolv delignification, high temperature ethanol/water environments, can be used to separate lignin, cellulose, and hemicelluloses in the bio-mass for bio-fuel production. These environments have been shown to induce stress corrosion cracking (SCC) in 316L stainless steel. Previous research has been done in mixed solvent environments at room temperature to understand SCC for stainless steels, but little is known about the behavior in high temperature environments. Simulated organosolv delignification environments were studied, varying water content, temperature, pHe, and Cl- content to understand how these constituents impact SCC. In order for SCC to occur in 316L, there needs to be between 10 and 90 volume % water and the environment needs to be at a temperature around 200°C. Once these two conditions are met, the environment needs to either have pHe < 4 or have more than 10 ppm Cl-. These threshold conditions are based on the organosolv delignification simulated environments tested. SCC severity was seen to increase as water content, temperature, and Cl- content increased and as pHe decreased. To prevent failure of industrial vessels encountering organosolv delignification environments, care needs to be taken to monitor and adjust the constituents to prevent SCC.
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Phan, Dan. "Atmospheric-Induced stress corrosion cracking of Austenitic Stainless Steels." Thesis, University of Manchester, 2009. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.508598.

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Brady, Michael P. "Evaluation of laser surface melting to mitigate chloride stress corrosion cracking in an austenitic stainless steel." Thesis, This resource online, 1990. http://scholar.lib.vt.edu/theses/available/etd-03122009-040851/.

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Salinas-Bravo, Victor Manuel. "Pitting and stress corrosion cracking of duplex stainless steels." Thesis, University of Manchester, 1991. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.493165.

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Iyer, Venkatramani S. "Effect of residual stress gradients in austenitic stainless steels on stress corrosion cracking." Thesis, Virginia Tech, 1991. http://hdl.handle.net/10919/42119.

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The effect of the residual stresses developed during simulated weld heat affected zone in austenitic stainless steel specimen on the stress corrosion cracking susceptibility was studied. Residual stresses was measured using X-ray diffraction technique. Boiling Magnesium Chloride was used as corrosive environment. Compressive stresses developed in the HAZ of the specimen and in regions away from the HAZ stress free values were obtained. The magnitude of the stress gradient decreased as the peak temperature attained during simulated welding decreased. Transgranular cracks were observed in the compressive stress gradient region and time to cracking decreased with increasing stress gradient. Higher nickel content alloys took longer to crack as opposed to lower nickel content alloys at approximately the same stress gradient.
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Sapiro, David O. "The Effects of Alloy Chemistry on Localized Corrosion of Austenitic Stainless Steels." Research Showcase @ CMU, 2017. http://repository.cmu.edu/dissertations/1087.

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This study investigated localized corrosion behavior of austenitic stainless steels under stressed and unstressed conditions, as well as corrosion of metallic thin films. While austenitic stainless steels are widely used in corrosive environments, they are vulnerable to pitting and stress corrosion cracking (SCC), particularly in chloride-containing environments. The corrosion resistance of austenitic stainless steels is closely tied to the alloying elements chromium, nickel, and molybdenum. Polarization curves were measured for five commercially available austenitic stainless steels of varying chromium, nickel, and molybdenum content in 3.5 wt.% and 25 wt.% NaCl solutions. The alloys were also tested in tension at slow strain rates in air and in a chloride environment under different polarization conditions to explore the relationship between the extent of pitting corrosion and SCC over a range of alloy content and environment. The influence of alloy composition on corrosion resistance was found to be consistent with the pitting resistance equivalent number (PREN) under some conditions, but there were also conditions under which the model did not hold for certain commercial alloy compositions. Monotonic loading was used to generate SCC in in 300 series stainless steels, and it was possible to control the failure mode through adjusting environmental and polarization conditions. Metallic thin film systems of thickness 10-200 nm are being investigated for use as corrosion sensors and protective coatings, however the corrosion properties of ferrous thin films have not been widely studied. The effects of film thickness and substrate conductivity were examined using potentiodynamic polarization and scanning vibrating electrode technique (SVET) on iron thin films. Thicker films undergo more corrosion than thinner films in the same environment, though the corrosion mechanism is the same. Conductive substrates encourage general corrosion, similar to that of bulk iron, while insulating substrates supported only localized corrosion.
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Books on the topic "Austenitic stainless steel Cracking"

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McIntyre, Dale R. Experience survey: Stress corrosion cracking of austenitic stainless steels in water. St.Louis: MTI International, 1987.

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Abraham, T. Stress corrosion cracking tests on high-level-waste container materials in simulated tuff repository environments. Washington, D.C: Division of Waste Management, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, 1986.

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Engineers, National Association of Corrosion. Protection od austenitic stainless steels and other austenitic alloysfrom polythionic acid stress corosion cracking during shutdown of refinery equipment. Houston: NACE, 1993.

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Engineers, National Association of Corrosion. Protection of austenitic stainless steels and other austenitic alloys from polythionic acid stress corrosion cracking during shutdown of refinery equipment. Houston: NACE, 1997.

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Chung, H. M. Irradiation-assisted stress corrosion cracking of model austenitic stainless steels irradiated in the Halden reactor. Washington, DC: Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1999.

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Chung, H. M. Irradiation-assisted stress corrosion cracking of model austenitic stainless steels irradiated in the Halden reactor. Washington, DC: Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1999.

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Chung, H. M. Irradiation-assisted stress corrosion cracking of model austenitic stainless steels irradiated in the Halden reactor. Washington, DC: Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1999.

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Ramchandani, Ajit. Nitriding of austenitic stainless steel. Birmingham: University of Aston. Department of Mechanical and Production Engineering, 1985.

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Kazior, Jan. Analiza czynników technologicznych decydujących o własnościach spiekanych austenitycznych stali nierdzewnych. Kraków: Politechnika Krakowska im. Tadeusza Kościuszki, 1994.

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Applications, AWS D18 Committee on Welding in Sanitary. Specification for welding of austenitic stainless steel tube and pipe systems in sanitary (hygienic) applications. Miami, Fla: The American Welding Society, 1999.

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Book chapters on the topic "Austenitic stainless steel Cracking"

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Folkhard, Erich. "Hot Cracking Resistance During the Welding of Austenitic Stainless Steels." In Welding Metallurgy of Stainless Steels, 144–71. Vienna: Springer Vienna, 1988. http://dx.doi.org/10.1007/978-3-7091-8965-8_5.

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Dayalan, Indhumathi, Prashant Frank Crasta, Sritam Pradhan, and Renu Gupta. "A Review on Stress Relaxation Cracking in Austenitic Stainless Steel." In Proceedings of International Conference on Intelligent Manufacturing and Automation, 427–34. Singapore: Springer Singapore, 2020. http://dx.doi.org/10.1007/978-981-15-4485-9_44.

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Matocha, Karel, and Jirí Wozniak. "Stress Corrosion Cracking Initiation in Austenitic Stainless Steel in High Temperature Water." In Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, 383–88. Hoboken, NJ, USA: John Wiley & Sons, Inc., 2013. http://dx.doi.org/10.1002/9781118787618.ch39.

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Karhu, Miikka, and Veli Kujanpää. "Solidification Cracking Studies in Multi Pass Laser Hybrid Welding of Thick Section Austenitic Stainless Steel." In Hot Cracking Phenomena in Welds III, 161–82. Berlin, Heidelberg: Springer Berlin Heidelberg, 2011. http://dx.doi.org/10.1007/978-3-642-16864-2_10.

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Chun, Eun-Joon, Hayato Baba, Kazutoshi Nishimoto, and Kazuyoshi Saida. "Evaluation of Solidification Cracking Susceptibility in Austenitic Stainless Steel Welds Using Laser Beam Welding Transverse-Varestraint Test." In Cracking Phenomena in Welds IV, 161–206. Cham: Springer International Publishing, 2016. http://dx.doi.org/10.1007/978-3-319-28434-7_9.

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Chung, H. M., W. E. Ruther, R. V. Strain, W. J. Shack, and T. M. Karlsen. "Irradiation-Assisted Stress Corrosion Cracking of Model Austenitic Stainless Steels." In Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, 931–39. Hoboken, NJ, USA: John Wiley & Sons, Inc., 2013. http://dx.doi.org/10.1002/9781118787618.ch98.

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Sumitomo, H. "Earing and Delayed Cracking of Deep-Drawn Cup of Austenitic Stainless Steel Sheets." In Advanced Technology of Plasticity 1987, 1289–96. Berlin, Heidelberg: Springer Berlin Heidelberg, 1987. http://dx.doi.org/10.1007/978-3-662-11046-1_77.

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Hojná, Anna, Miroslava Ernestová, Ossi Hietanen, Ritva Korhonen, Ludmila Hulinová, and Ferenc Oszvald. "Irradiation Assisted Stress Corrosion Cracking of Austenitic Stainless Steel WWER Reactor Core Internals." In 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, 1257–72. Hoboken, New Jersey, Canada: John Wiley & Sons, Inc., 2012. http://dx.doi.org/10.1002/9781118456835.ch131.

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Hojná, Anna, Miroslava Ernestová, Ossi Hietanen, Ritva Korhonen, Ludmila Hulinová, and Ferenc Oszvald. "Irradiation Assisted Stress Corrosion Cracking of Austenitic Stainless Steel WWER Reactor Core Internals." In Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors, 1257–75. Cham: Springer International Publishing, 2011. http://dx.doi.org/10.1007/978-3-319-48760-1_77.

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Sowards, J. W., B. T. Alexandrov, John Lippold, and G. S. Frankel. "Weldability of a New Ni-Cu Welding Consumable for Joining Austenitic Stainless Steels." In Hot Cracking Phenomena in Welds III, 393–413. Berlin, Heidelberg: Springer Berlin Heidelberg, 2011. http://dx.doi.org/10.1007/978-3-642-16864-2_20.

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Conference papers on the topic "Austenitic stainless steel Cracking"

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Hapsoro, Padang Wikar. "Stress Corrosion Cracking on an Insulated Austenitic Stainless Steel Pressure Vessel." In SPE/IATMI Asia Pacific Oil & Gas Conference and Exhibition. Society of Petroleum Engineers, 2017. http://dx.doi.org/10.2118/186287-ms.

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Kalnaus, Sergiy, Feifei Fan, and Yanyao Jiang. "Fatigue and Cyclic Plasticity Properties of a Super-Austenitic Stainless Steel." In ASME 2007 Pressure Vessels and Piping Conference. ASMEDC, 2007. http://dx.doi.org/10.1115/pvp2007-26478.

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Tension-compression, torsion and axial-torsion experiments were conducted on AL-6XN® alloy. The main goal was to investigate experimentally, in detail, the cyclic plasticity behavior as well as fatigue life of AL-6XN® steel. Details of cyclic stress-strain response were collected during the experiments, which can serve as a baseline for development of cyclic plasticity model for this material. Microscopic observations of cracking behavior conducted in the present study allow connecting the fracture mechanism with fatigue life prediction. It was observed, that fatigue life of this material is a function of the fracture mode (mixed or tensile). The mixed cracking was observed in the specimens tested under higher applied strain levels, while the tensile cracking was revealed in the tests under lower strain amplitudes. Strain-life curves of the specimens failed in mixed mode and of those failed in tensile mode run parallel to each other, but the specimens that exhibit mixed failure mode show lower fatigue life as compared to the tensile mode specimens. Transition between mixed and tensile cracking orientations was studied in detail. The results of the experimental work presented in this study can serve for design of fatigue models for this material in the future.
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Chen, Y., B. Alexandreanu, W. J. Shack, K. Natesan, and A. S. Rao. "Cyclic Crack Growth Rate of Irradiated Austenitic Stainless Steel Welds in Simulated BWR Environment." In ASME 2011 Pressure Vessels and Piping Conference. ASMEDC, 2011. http://dx.doi.org/10.1115/pvp2011-57728.

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Reactor core internal components in light water reactors are subjected to neutron irradiation. It has been shown that the austenitic stainless steels used in reactor core internals are susceptible to stress corrosion cracking after extended neutron exposure. This form of material degradation is a complex phenomenon that involves concomitant conditions of irradiation, stress, and corrosion. Interacting with fatigue damage, irradiation-enhanced environmental effects could also contribute to cyclic crack growth. In this paper, the effects of neutron irradiation on cyclic cracking behavior were investigated for austenitic stainless steel welds. Post-irradiation cracking growth tests were performed on weld heat-affected zone specimens in a simulated boiling water reactor environment, and cyclic crack growth rates were obtained at two doses. Environmentally enhanced cracking was readily established in irradiated specimens. Crack growth rates of irradiated specimens were significantly higher than those of nonirradiated specimens. The impact of neutron irradiation on environmentally enhanced cyclic cracking behavior is discussed for different load ratios.
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Janulionis, Remigijus, Gintautas Dundulis, and Renatas Karalevicˇius. "Evaluation of the Inter Granular Stress Corrosion Cracking Defects in Austenitic Stainless Steel Piping." In 17th International Conference on Nuclear Engineering. ASMEDC, 2009. http://dx.doi.org/10.1115/icone17-75317.

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The Inter Granular Stress Corrosion Cracking (IGSCC) is a dominant damage mechanism of the austenitic stainless steel. The primary circuit piping of RBMK type reactors is produced from austenitic stainless steel 08×18H10T. Defects in welded joints of pipes with nominal diameter of 300 mm were detected during In-service inspections [1]. Metallographic investigations defined that crack growth mechanism is IGSCC. The appearance of defects increases the probability of RCS piping failures of these pipes. A leak or break in RCS piping is not acceptable from safety and political (society risk) points of view. According this the evaluation of these cracks is very important for safe operation of this type reactor. The procedures for IGSCC crack evaluation consist of two parts. The first part is determination of the acceptable crack size for the component with crack, and the second part is the crack growth calculation. The acceptable flaw size provides information about the largest flaw size which component can tolerate without failure with accepted safety factors. The crack growth calculation determines how long does it take for the existing crack to reach the maximal acceptable size. The results of these calculations (acceptable crack size and crack growth) determine the further inspection schedule of the components with crack. The objective of this paper is the evaluation of the IGSCC defects detected during In-Service inspection in the primary circuit piping which outside diameter of piping is 325 mm, the wall thickness – 16 mm. Detected cracks were evaluated using method R6 [2]. The IGSCC crack growing analysis was performed using methodology presented in document [3]. The prognosis results were compared with crack data detected during In-service inspection. According analysis results were determined that the IGSCC defects detected during In-service inspection can be left without repairing for 1.5 years operation.
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Xu, Shugen, Weiqiang Wang, and Huadong Liu. "The Stress Corrosion Cracking of Austenitic Stainless Steel Heat Exchange Tubes: Three Cases Study." In ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference. ASMEDC, 2010. http://dx.doi.org/10.1115/pvp2010-25217.

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In this paper, three leakage failure cases of heat exchange tubes have been introduced. The reasons of the leakage for austenitic stainless steel tubes and overlay welding layer on the tube sheet have been analyzed. Through the investigation of the operation process and histories of the equipment, and after chemical compositions analysis of tube material and corrosion products, metallographic test of specimens with cracks, and fracture surface scan with Scanning Electron Microscope (SEM), the cracking reason and mode are described as the Stress Corrosion Cracking (SCC) of austenitic stainless steel. This kind of cracking in three cases was induced by the micro chloride in the high temperature water (or steam). Moreover, sulfide and dissolved oxygen also reduced the threshold value of chloride concentration and enhanced the corrosion rate for SCC. The cracking mode of Case A and B are transgranular; and Case C is intergranular. It indicates that for this kind of in-service heat exchanger, the operators should not only control the chloride concentration in feed water, but also the sulfide and dissolved oxygen in the future. The austenitic stainless steel tubes (China steel types-1Cr18Ni9Ti and 0Cr18Ni10Ti, equal to Type 304 and Type 321 according to ASME code) used in this cases are not fit to this condition. Thus, for the new heat exchanger design, the tube material should be changed into austenitic-ferritic (duplex phase) steel, such as 2205 Series, which has an excellent performance for SCC resistance in the high temperature water (or steam) with chloride.
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Chen, Bo, Michael W. Spindler, David J. Smith, and Peter E. J. Flewitt. "Effect of Thermo-Mechanical History on Reheat Cracking in 316H Austenitic Stainless Steel Weldments." In ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference. ASMEDC, 2010. http://dx.doi.org/10.1115/pvp2010-25088.

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Reheat cracking has been observed in the heat affected zone of the 316H austenitic stainless steel thick section weldments during service at a temperature of ∼500°C. This has been attributed to the creep dominated relaxation of the highly triaxial residual stresses. Here the role of thermo-mechanical variables that contribute to the susceptibility of thick section 316H austenitic stainless steel weldments is briefly reviewed. The influence of the plastic strain, carbide precipitation and impurity element segregation on the subsequent creep deformation behaviour and the susceptibility to creep cavitation damage is discussed. A systematically designed experiment which includes these parameters has been undertaken for a 316H austenitic stainless steel. In addition, residual stress profiles have been introduced into cylindrical pre-treated specimens and the relaxation of these profiles with heat treatment has been measured by neutron diffraction. The experimental results are considered with respect to the effect of the microstructure on subsequent creep deformation and stress relaxation. The susceptibility to intergranular brittle fracture is discussed and an attempt is made to correlate the microstructure and stress state factors encountered in the HAZ with the accumulation of the creep cavitation associated with reheat cracking.
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Lisowyj, Bob, and Zoran Kuljis. "Determining the Onset of Stress Corrosion Cracking in Austenitic Stainless Steel With Permeability Change." In ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference. ASMEDC, 2010. http://dx.doi.org/10.1115/pvp2010-25984.

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After two decades of operation, austenitic stainless steel Control Element Drive Mechanism (CEDM) seal housings at a Pressurized Water Reactor (PWR) nuclear plant experienced Transgranular Stress Corrosion Cracking (TGSCC). In order to prevent the same cracking from occurring at the Fort Calhoun Nuclear Plant, a preventative program was initiated in 1999. All 37 CEDM seal housings have been inspected by using WesDyne Intraspect pancake and plus point eddy current probes. Examination of the eddy current data found that TGSCC was associated with localized areas of higher permeability (confirmed with a magnetometer). In order to quantitatively analyze the data, the normalized value from signal amplitude was defined as the arithmetic ratio between the absolute measurement of local permeability value (amplitude) and the eddy current signal value (amplitude) for the calibration standard axial notch. The data showed that in failed seal housings the normalized amplitudes were about three times greater than in non-cracked housings. Higher permeabilities were associated with cracked locations. The eddy current methodology therefore provides an empirical criterion to monitor when locally higher surface material permeability changes occur in order to determine the onset of TGSCC.
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Wenman, Mark, James Barton, Kenneth Trethewey, Sean Jarman, and Paul Chard-Tuckey. "Finite Element Modelling of Transgranular Chloride Stress Corrosion Cracking in 304L Austenitic Stainless Steel." In ASME 2008 Pressure Vessels and Piping Conference. ASMEDC, 2008. http://dx.doi.org/10.1115/pvp2008-61262.

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Austenitic stainless steels (ASS) have excellent resistance to general corrosion. However, these steels can be susceptible to localised corrosion such as pitting and crevice corrosion. In the presence of a tensile stress they can also exhibit stress corrosion cracking (SCC). In pressurised water reactor (PWR) nuclear plant incidents of SCC, especially chloride-induced SCC (CISCC), have been observed. Chloride ions which can lead to CiSCC of even low carbon austenitic grades can be introduced from many sources including the atmosphere and materials introduced into the reactor environment. Stress can result from primary loading or introduced as secondary stresses, such as residual stress, through machining or welding processes. Residual stresses are internal self-balancing stresses that can act alone or together with a primary stress to cause premature failure of a component. 15 mm lengths of 304L ASS tube were subjected to an in-plane compression of between 1–10 mm before unloading. This created regions of plasticity and on relaxation the specimen contains a complex state of residual stresses that can be modelled by finite element (FE) methods. The tube specimens were then boiled in MgCl2 for 14 days before metallographic examination. A FE model of transgranular CISCC has been created by writing a VUMAT user subroutine implemented into the commercial FE code ABAQUS. The model is based on simple rules which include the initiation of surface corrosion pits from which, under mechanical control, SCC cracks may propagate. The model includes rules for SCC growth, based on hydrostatic stress state, and can incorporate the idea of grain orientation effects. Cracks created interact with and modify the residual stress field in the tube. Test results were then compared with model outputs. Crack morphologies and to a certain extent crack positions matched well with experiment. Attempts were made to calculate the crack tip driving forces from the model. The results also highlight the need to consider the importance of triaxial stress states, created by pits and cracks, and stress as a tensor rather than a scalar property. The effect of grain misorientation is also investigated, but so far, found to be of more limited importance for modelling transgranular CISCC.
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Pornpibunsompop, Tosapolpom. "Pitting corrosion and stress corrosion cracking of austenitic stainless steel in acidic chloride environment." In 2018 5th Asian Conference on Defense Technology (ACDT). IEEE, 2018. http://dx.doi.org/10.1109/acdt.2018.8593077.

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JANOUŠEK, Jaromír, Fabio SCENINI, Liberato VOLPE, Anna HOJNÁ, and Mary Grace BURKE. "Environmentally-Assisted Cracking of Type 316L Austenitic Stainless Steel in a Hydrogenated Steam Environment." In METAL 2019. TANGER Ltd., 2019. http://dx.doi.org/10.37904/metal.2019.706.

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Reports on the topic "Austenitic stainless steel Cracking"

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Jackson, J. H., S. P. Teysseyre, and M. P. Heighes. Irradiation Assisted Stress Corrosion Cracking of Austenitic Stainless Steel in BWR Conditions. Office of Scientific and Technical Information (OSTI), June 2017. http://dx.doi.org/10.2172/1408502.

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Chen, Y., O. K. Chopra, Eugene E. Gruber, and William J. Shack. Irradiation-Assisted Stress Corrosion Cracking of Austenitic Stainless Steels in BWR Environments. Office of Scientific and Technical Information (OSTI), June 2010. http://dx.doi.org/10.2172/1224951.

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Whorlow, K. M., and F. B. Jr Hutto. Effects of fluoride and other halogen ions on the external stress corrosion cracking of Type 304 austenitic stainless steel. Office of Scientific and Technical Information (OSTI), July 1997. http://dx.doi.org/10.2172/505259.

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Chung, H. M., and W. J. Shack. Irradiation-assisted stress corrosion cracking behavior of austenitic stainless steels applicable to LWR core internals. Office of Scientific and Technical Information (OSTI), January 2006. http://dx.doi.org/10.2172/915725.

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Chen, Y., O. K. Chopra, W. K. Soppet, Nancy L. Dietz Rago, and W. J. Shack. Irradiation-Assisted Stress Corrosion Cracking of Austenitic Stainless Steels and Alloy 690 from Halden Phase-II Irradiations. Office of Scientific and Technical Information (OSTI), September 2008. http://dx.doi.org/10.2172/1224948.

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Chen, Y., O. K. Chopra, W. K. Soppet, W. J. Shack, Y. Yang, and T. R. Allen. Cracking behavior and microstructure of austenitic stainless steels and alloy 690 irradiated in BOR-60 reactor, phase I. Office of Scientific and Technical Information (OSTI), February 2010. http://dx.doi.org/10.2172/972196.

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Anderl, R. A., and P. K. Nagata. Helium permeability through austenitic stainless steel. Office of Scientific and Technical Information (OSTI), September 1989. http://dx.doi.org/10.2172/7171431.

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Brady, Michael P., Yukinori Yamamoto, Govindarajan Muralidharan, Hiram Rogers, and Bruce A. Pint. Deployment of Alumina Forming Austenitic (AFA) Stainless Steel. Office of Scientific and Technical Information (OSTI), October 2013. http://dx.doi.org/10.2172/1097493.

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Switzner, Nathan, Ted Neidt, John Hollenbeck, J. Knutson, Wes Everhart, R. Hanlin, R. Bergen, and D. K. Balch. HYDROGEN-ASSISTED FRACTURE IN FORGED TYPE 304L AUSTENITIC STAINLESS STEEL. Office of Scientific and Technical Information (OSTI), September 2012. http://dx.doi.org/10.2172/1134047.

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Brady, M. P., and W. J. Matthews. Evaluation of Alumina-Forming Austenitic Stainless Steel Alloys in Microturbines. Office of Scientific and Technical Information (OSTI), September 2010. http://dx.doi.org/10.2172/988341.

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