Microstructures and mechanical properties of welded Fe-12Cr-20Mn austenitic stainless steel

Eldridge, I. J.; Morrison, David J.

doi:10.1007/bf02645258

Cited by 3 publications

(1 citation statement)

References 14 publications

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“…Hence if the microstructural changes in the HAZ are not controlled as a result of improper selection of welding variables, the resulting metallurgical structures may be undesirable, and as a consequence, poor weld joint quality may be produced (Bipin and Tewan, 2010;Bodude and Momohjimoh, 2015). Choosing suitable welding variables that will produce balanced (optimum or acceptable) HAZ microstructure is one profound means by which weld joint integrity can be ensured and improved (Eldridge and Morrison, 1994;Akor and Tuleun, 2014). Therefore, adequate and fundamental understanding of the behaviour of 304L austenitic stainless steel under varied welding variables is necessary, if incidences of weld joints failures are to be mitigated.…”

Section: Introductionmentioning

confidence: 99%

Effects of Welding Power Input on the Microstructure and Impact Toughness of the Heat Affected Zone of 304L Austenitic Stainless Steel

et al. 2019

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The effects of welding power input on the microstructural characteristics and impact behaviour of the Heat Affected Zone (HAZ) of type 304L austenitic stainless steel were investigated. This is with a view to optimize the welding process and ensure high weldment integrity of the heat affected zone. Chemical analysis of the as-received 304L austenitic stainless steel was determined using an Optical Emission Spectrometry AR 4 30 metal analyzer. Thereafter, 30 samples of the as-received 304L austenitic stainless steel plate with dimensions of 70 mm length, 45 mm breadth and 8 mm thickness were cut and labeled into A, B and C each of 10 numbers. The grouped samples were further cut into two equal halves with hacksaw and welded using Gas Metal Arc Welding (GTAW) process and 304L electrode to produce butt joint HAZ square geometry samples. The obtained HAZ and as-received samples were machined to standard charpy impact test specimens. Also, the HAZ and as-received specimens were prepared for microscopy studies using optical microscopy. Results obtained showed that the microstructures are composed majorly of mixture of austenite and ferrite phases, also variations in volume fraction and grain size of the phases were observed under varied range of power input. In addition, chromium carbide formation and precipitation due to sensitization was seen at the grain boundaries. Optimum impact toughness (IT) of 42 J was obtained for HAZ sample at power input of 12.0 KW while the least IT of 39 J was obtained from sample welded using power input of 4.6 KW as compared with the as-received with IT of 58 J.Keywords - 304L austenitic stainless steel; gas metal arc welding; impact toughness; microstructures;

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Section: Introductionmentioning

confidence: 99%

Effects of Welding Power Input on the Microstructure and Impact Toughness of the Heat Affected Zone of 304L Austenitic Stainless Steel

et al. 2019

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Effects of ion irradiation on fatigue of Fe-12Cr-20Mn stainless steel for fusion reactor applications

Tulluri

Morrison

1997

J. of Materi Eng and Perform

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To minimize waste disposal problems associated with the residual radioactivity of the first wall material of a fusion reactor, fast induced radioactive decay (FIRD) alloys based on the Fe-Cr-Mn system are being investigated. The objective of this research was to evaluate the effects of irradiation on cyclic strain localization and fatigue crack initiation in a FIRD Fe-12Cr-20Mn alloy and to compare the response to commercially available 316 stainless steel. The alloys were irradiated with 200 keV Fe ions to a dose of I x 1016 ions/cm 2 and 15.5 keV He ions to a dose of 7 • 1015 ions/era 2 to simulate the irradiation-induced defect structure and helium concentration that would be produced in a fusion reactor. Irradiated specimens were fatigued in a cantilever beam fatigue testing machine with the deflection set to produce a fully reversed total strain amplitude of 0.25 % on the surface of the specimen. Acetate replicas were obtained during the fatigue tests to provide a record of surface fatigue damage. Transmission electron microscopy (TEM) analyses were performed to characterize the microstructural changes resulting from the irradiations and interactions between fatigue-induced glide dislocations and the irradiation-induced defects.Results indicate that the irradiated Fe-Cr-Mn alloy exhibits fatigue properties similar to 316 stainless steel. Glide dislocations produced by fatigue cycling annihilate irradiation-induced defects. The defect annihilation causes the formation of cleared channels in which the cyclic plastic strain is localized. Subsurface slip bands penetrate the irradiated regions through the cleared channels and serve as fatigue crack initiation sites.

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Reduced activation Fe-Cr-Mn austenitic steels for nuclear power plants

Demina

Prusakova

Roshchin

et al. 2010

Inorg. Mater. Appl. Res.

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Microstructures and mechanical properties of welded Fe-12Cr-20Mn austenitic stainless steel

Cited by 3 publications

References 14 publications

Effects of Welding Power Input on the Microstructure and Impact Toughness of the Heat Affected Zone of 304L Austenitic Stainless Steel

Effects of Welding Power Input on the Microstructure and Impact Toughness of the Heat Affected Zone of 304L Austenitic Stainless Steel

Effects of ion irradiation on fatigue of Fe-12Cr-20Mn stainless steel for fusion reactor applications

Reduced activation Fe-Cr-Mn austenitic steels for nuclear power plants

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