Abdullah Sinjlawi

ORCID: 0009-0007-3753-833X
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About
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Research Areas
  • Hydrogen embrittlement and corrosion behaviors in metals
  • Fusion materials and technologies
  • Nuclear Materials and Properties
  • Concrete Corrosion and Durability
  • High Temperature Alloys and Creep
  • Material Properties and Failure Mechanisms

University of Michigan
2023-2024

Korea Advanced Institute of Science and Technology
2020

Irradiation assisted stress-corrosion cracking (IASCC) is a form of intergranular stress corrosion that occurs in irradiated austenitic alloys. It requires an microstructure along with high temperature water and stress. The process ubiquitous it wide range alloys chemistries, but only when the alloy irradiated. Despite evidence this degradation mode dates back to 1960s, mechanism by which has remained elusive. Here, using resolution electron backscattering detection analyze local...

10.1016/j.pmatsci.2024.101255 article EN cc-by-nc-nd Progress in Materials Science 2024-02-16

The crevice stress corrosion cracking (SCC) susceptibility of austenitic stainless steels was evaluated in simulated pressurized water reactor (PWR) environments. To simulate the abnormal condition temporary clamping devices on leaking small bore pipes, bent beam (CBB) tests were performed oxygenated as well hydrogenated conditions. No SCC cracks found for SS316 both SS304 also showed good resistance condition. However, all specimens condition, indicating poor resistance. It that residual...

10.1016/j.net.2020.04.023 article EN cc-by-nc-nd Nuclear Engineering and Technology 2020-04-28
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