Development and in-depth experimental characterization of novel TiZrNbHfTaOx reinforced 316L stainless steel for advanced nuclear applications

MakaleAçık ErişimScopus SJRQ1

Özet

Oxide Dispersion Strengthened (ODS) materials are known for their exceptional performance in high-temperature and radiation environments. This study explores the radiation shielding properties of 316L Stainless Steel reinforced with TiZrNbHfTaOx High-Entropy Oxide (HEO). By integrating HEOs into the 316L stainless steel matrix, we aim to enhance its structural and radiation shielding properties. The HEO was synthesized using high-energy ball milling and oxidation processes, followed by thorough characterization using X-ray diffraction (XRD), scanning electron microscopy (SEM), and energy-dispersive spectroscopy (EDS). Our results indicate significant improvements in both gamma-ray and neutron shielding properties. The 316L SS samples reinforced with 20 % HEO exhibited the highest mass attenuation coefficients (MAC), lowest half-value layers (HVL), and highest effective atomic numbers (Zeff) across all tested photon energies. These enhancements are attributed to the high atomic number elements and unique synergistic effects of HEOs. Neutron shielding was evaluated through equivalent dose rate measurements, with the 20 % HEO sample demonstrating the highest absorbed dose rate percentage and superior neutron interaction cross-sections. Benchmarking against standard materials confirmed the superior performance of HEO-reinforced 316L SS, making it a promising candidate for advanced radiation shielding in nuclear reactors and other high-radiation environments. Our findings suggest that HEO reinforcement not only improves mechanical properties but also significantly enhances the radiation protection capabilities of 316L stainless steel.

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AlanDeğerDil
dc.contributor.authorGüler, Ömer
dc.contributor.authorAlbayrak, M. Gökhan
dc.contributor.authorBaşgöz, Öyküm
dc.contributor.authorKavaz, E.
dc.contributor.authorAlkarrani, Hessa
dc.contributor.authorALMisned, Ghada
dc.contributor.authorTekin, H.O.
dc.date.accessioned2026-10-28T14:54:40.390002504Z
dc.date.available2026-10-28T14:54:40.390002504Z
dc.date.issued2024
dc.description.abstractOxide Dispersion Strengthened (ODS) materials are known for their exceptional performance in high-temperature and radiation environments. This study explores the radiation shielding properties of 316L Stainless Steel reinforced with TiZrNbHfTaOx High-Entropy Oxide (HEO). By integrating HEOs into the 316L stainless steel matrix, we aim to enhance its structural and radiation shielding properties. The HEO was synthesized using high-energy ball milling and oxidation processes, followed by thorough characterization using X-ray diffraction (XRD), scanning electron microscopy (SEM), and energy-dispersive spectroscopy (EDS). Our results indicate significant improvements in both gamma-ray and neutron shielding properties. The 316L SS samples reinforced with 20 % HEO exhibited the highest mass attenuation coefficients (MAC), lowest half-value layers (HVL), and highest effective atomic numbers (Zeff) across all tested photon energies. These enhancements are attributed to the high atomic number elements and unique synergistic effects of HEOs. Neutron shielding was evaluated through equivalent dose rate measurements, with the 20 % HEO sample demonstrating the highest absorbed dose rate percentage and superior neutron interaction cross-sections. Benchmarking against standard materials confirmed the superior performance of HEO-reinforced 316L SS, making it a promising candidate for advanced radiation shielding in nuclear reactors and other high-radiation environments. Our findings suggest that HEO reinforcement not only improves mechanical properties but also significantly enhances the radiation protection capabilities of 316L stainless steel.
dc.description.sponsorshipPrincess Nourah Bint Abdulrahman University, PNU, (PNURSP2024R149)
dc.description.sponsorshipPrincess Nourah Bint Abdulrahman University, PNU
dc.identifier.articlenumber113516
dc.identifier.doi10.1016/j.nucengdes.2024.113516
dc.identifier.eissn1872-759X
dc.identifier.issn0029-5493
dc.identifier.scopus2-s2.0-85200642243
dc.identifier.urihttps://rdlopen.rawdatalibrary.net/r/munzur/1872
dc.identifier.volume428
dc.identifier.wosWOS:001291549900001
dc.language.isoen
dc.publisherElsevier Ltd
dc.relation.ispartofNuclear Engineering and Design
dc.rightsinfo:eu-repo/semantics/openAccess
dc.subject316L stainless steel
dc.subjectHigh-entropy oxide
dc.subjectNuclear applications
dc.subjectRadiation
dc.subject.otherAtoms
dc.subject.otherBall milling
dc.subject.otherBenchmarking
dc.subject.otherEnergy dispersive spectroscopy
dc.subject.otherEntropy
dc.subject.otherGamma rays
dc.subject.otherHigh-entropy alloys
dc.subject.otherNeutron irradiation
dc.subject.otherNeutrons
dc.subject.otherNiobium alloys
dc.subject.otherRadiation shielding
dc.subject.otherReinforcement
dc.subject.otherScanning electron microscopy
dc.subject.otherTantalum alloys
dc.subject.otherTitanium alloys
dc.subject.otherZircaloy
dc.subject.other20 highs
dc.subject.other316 L stainless steel
dc.subject.other316L SS
dc.subject.otherExperimental characterization
dc.subject.otherHigh radiation environment
dc.subject.otherHigh-entropy oxide
dc.subject.otherNeutron shielding
dc.subject.otherNuclear application
dc.subject.otherPerformance
dc.subject.otherShielding properties
dc.subject.otherAustenitic stainless steel
dc.titleDevelopment and in-depth experimental characterization of novel TiZrNbHfTaOx reinforced 316L stainless steel for advanced nuclear applications
dc.typeArticle
rdl.citation.openalex13
rdl.citation.scopus12
rdl.oa.statushybrid
rdl.oa.statusclosed
rdl.oa.statusgreen
rdl.oa.urlhttps://hdl.handle.net/11508/58702
rdl.scopus.quartileQ1
rdl.source.indexSCOPUS
rdl.source.indexWOS