Global ETD Search

Search theses and dissertations gathered from participating repositories worldwide. Every result links back to the library that holds it. No account is needed.

Results

Showing 1 to 5 of 5 for “"intergranular stress corrosion cracking"”.

  1. Stress corrosion cracking of nuclear grade steels

    … pressure vessel steel were studied for their stress corrosion cracking susceptibility. Cylindrical tensile specimens were subjected to slow strain rate testing at 75°C in aerated, aqueous solutions (distiled water with 1000ppm Cl⁻ or SO₄ = ions in solution) in a range of corrosion potentials. …

    cape-town Repository record for Stress corrosion cracking of nuclear grade steels (opens in a new tab)

  2. Impact of grain boundary character on the radiation-induced segregation morphology in proton-irradiated 316L austenitic stainless steel

    … This may have important implications for intergranular stress corrosion cracking studies, grain boundary engineering proposals, and future predictive studies on the microstructural evolution in irradiated alloys.

    uiuc Repository record for Impact of grain boundary character on the radiation-induced segregation morphology in proton-irradiated 316L austenitic stainless steel (opens in a new tab)

  3. Influence of heat treatment condition on the stress corrosion cracking properties of low pressure turbine blade steel FV520B

    Stress corrosion cracking (SCC) is a corrosion phenomenon which continues to plague the power generating industry especially in low pressure (LP) steam turbine blades operating in the phase transition zone. An investigation has therefore been conducted to examine the effect of heat treatment …

    cape-town Repository record for Influence of heat treatment condition on the stress corrosion cracking properties of low pressure turbine blade steel FV520B (opens in a new tab)

  4. Oxidation kinetics of 316l stainless steel in the pressurised water reactor environment

    … to improving the prediction of primary water stress corrosion cracking in austenitic stainless steels, this investigation measured the oxide growth kinetics of 316L stainless steel when exposed to a simulated primary water environment of a pressurised water reactor (PWR). It is generally …

    cape-town Repository record for Oxidation kinetics of 316l stainless steel in the pressurised water reactor environment (opens in a new tab)

  5. An Analysis of Microstructure and Corrosion Resistance in Underwater Friction Stir Welded 304L Stainless Steel

    … the UWFSWs were found less susceptible to corrosion than arc welds due to the subsurface location of the sensitization bands. A SCC analysis of UWFSWs relative to base metal and arc weldments was performed. U-bends were exposed to two 3.5% NaCl cyclic immersion experiments at 21 °C and 63 …

    byu Repository record for An Analysis of Microstructure and Corrosion Resistance in Underwater Friction Stir Welded 304L Stainless Steel (opens in a new tab)