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Complexity of segregation behavior at localized deformation sites formed while in service in a 316 stainless steel baffle-former bolt

Journal Article · · Scripta Materialia
Here, post-irradiation evaluation was performed on a 316 stainless steel baffle former bolt harvested after 40 years of service in a pressurized water reactor. Microstructure analysis revealed the presence of defect-free dislocation channels and strain-induced twins, indicative of loading at a stress level close to yield stress at least once while in service. Primary radiation-induced Ni/Si precipitates were destroyed during channel and twin formation, and secondary, significantly coarser Ni/Si precipitates formed along newly formed Σ3 boundaries during the continued irradiation. Additionally, an elevated phosphorus level was observed inside the strain-induced twin. Complex chemistry inside the strain-induced feature may overlap with dislocation pileups and impact localized corrosion, material long-term performance, and safety.
Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE), Nuclear Fuel Cycle and Supply Chain. Advanced Fuel Campaign
Grant/Contract Number:
AC05-00OR22725
OSTI ID:
2441084
Alternate ID(s):
OSTI ID: 2440917
Journal Information:
Scripta Materialia, Journal Name: Scripta Materialia Vol. 255; ISSN 1359-6462
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

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