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Assessing the influence of welding-induced mechanics on oxidation and stress corrosion cracking in an Alloy 600-Alloy 152 M weldment under simulated PWR primary water.
- Source :
-
Journal of Nuclear Materials . Dec2024, Vol. 601, pN.PAG-N.PAG. 1p. - Publication Year :
- 2024
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Abstract
- • Higher residual stress/strain and dislocation density in alloy 600 HAZ than in base. • Thicker oxide and deeper intergranular oxidation in alloy 600 HAZ than in base. • Longer SCC length and higher cracking engagement in alloy 600 HAZ than in base. • Stress-assisted oxidation contributes to enhanced SCC growth in alloy 600 HAZ. • The impact of local mechanical parameters on SCC in the HAZ is highlighted. The impact of welding-induced mechanics on the oxidation and stress corrosion cracking (SCC) behavior of Alloy 600 in a pressurized water reactor (PWR) primary water was investigated using an Alloy 600-Alloy 152 M weldment. The microstructural analysis found a 0.05 mm-wide composition transition zone from welding. The Alloy 600 heat-affected zone (HAZ) grain size matches the Alloy 600 base (600B). Deformation hardening initially decreases and stabilizes from the fusion boundary (FB) to the 600B Comparing the microstructural characteristics of the specimen from the HAZ at about 0.5 mm from the FB with specimen 600B shows identical composition, but the former exhibits higher Vickers hardness (HV), kernel average misorientation (KAM), dislocation density, and residual stresses. Results from both short- and long-term oxidation tests indicate that the specimen from the HAZ exhibits a greater thickness of the inner oxide film, a higher number of local oxidation sites, and an increased maximum depth of intergranular (IG) oxidation compared to the 600B specimen. Multiple sets of SCC test results demonstrate that the crack growth rate (CGR) in the specimens from the HAZ is higher than that in the base, with the former showing longer IG cracks and a greater proportion of IG cracking. [ABSTRACT FROM AUTHOR]
Details
- Language :
- English
- ISSN :
- 00223115
- Volume :
- 601
- Database :
- Academic Search Index
- Journal :
- Journal of Nuclear Materials
- Publication Type :
- Academic Journal
- Accession number :
- 179321783
- Full Text :
- https://doi.org/10.1016/j.jnucmat.2024.155349