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Hydrogen embrittlement of duplex steel tested using slow strain rate test
Metalurgija, 2014 This paper is dealing with hydrogen embrittlement of austenitic-ferritic 2205 duplex steel using the slow strain rate test (SSRT). The original material was subjected to heat treatment under 700 °C during 5 hours and following aircooling with the aim of ...
P. Vaňova, J. Sojka
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Susceptibility of Dissimilar IN600 Welded Joints to Stress Corrosion Cracking Using Slow Strain Rate Test in Sodium Electrolytes [PDF]
Metals, 2022 The stress corrosion cracking (SCC) behavior of aged plates of Inconel 600 welded to Inconel 600 plates in the as-received condition was studied using the slow strain rate test (SSRT) in two sodium containing electrolytes at 25 and 80 °C.
Heriberto Granados-Becerra +6 more
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Materials and Design, 2021 A new accelerated creep assessment method to evaluate the creep performance of metals and alloys from high-temperature tensile tests, i.e. slow-strain-rate testing (SSRT), is proposed and evaluated. The method consists of decomposing the inelastic strain into a plastic and creep component by adopting general assumptions on the inelastic strain ...
V Norman, Mattias Calmunger
exaly +4 more sources
An Approach to Estimate SCC Growing Rate in Slow Strain Rate Tensile Test Based on EPFEM [PDF]
Advances in Materials Science and Engineering, 2019 The slow strain rate tensile test (SSRT) is a common means to investigate stress corrosion cracking (SCC) in key engineering structural materials of light-water reactors, and it is an important task to real-time monitor the crack growing length and rate ...
Shuai Wang +4 more
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European Journal of MaterialsAustenitic stainless steels, such as Sanicro 25 and Sanicro 28, exhibit excellent mechanical properties at elevated temperatures. This study investigates their time-dependent deformation behaviours through two distinct testing methods: slow strain rate ...
Jinghao Xu +2 more
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Slow strain rate testing of welded copper
, 2013 In Sweden spent nuclear fuel is planned to be placed 500 m down in the bedrock. The spent nuclear fuel will be contained in copper canisters. The reason behind the selection of copper is its thermodynamic stability against corrosion in the depository. The copper will be exposed to mechanical loading and will be plastically deformed due to creep.
Kirti Teja Pasupuleti
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Nuclear Materials and EnergyPrecipitation-hardened Cu–Cr–Zr alloy is proposed as a heat sink material for various components of the ITER owing to its high strength, high conductivity, and superior resistance against neutron irradiation. Oxide-dispersion-strengthened copper (ODS-Cu)
M. Hatakeyama +6 more
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A stress corrosion cracking test with slow strain rate and constant current [PDF]
, 1977 R.S. Ondrejcin
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