Atıf İçin Kopyala
Say Y., Güler Ö., Kavaz E., Almisned G., Ene A., Tekin H. O.
OPEN CHEMISTRY, cilt.21, sa.1, ss.1-10, 2023 (SCI-Expanded)
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Yayın Türü:
Makale / Tam Makale
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Cilt numarası:
21
Sayı:
1
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Basım Tarihi:
2023
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Doi Numarası:
10.1515/chem-2022-0307
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Dergi Adı:
OPEN CHEMISTRY
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Derginin Tarandığı İndeksler:
Science Citation Index Expanded (SCI-EXPANDED), Scopus, CAB Abstracts, Veterinary Science Database, Directory of Open Access Journals
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Sayfa Sayıları:
ss.1-10
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Anahtar Kelimeler:
austenitic stainless steels, nuclear materials, characterization, CORROSION-RESISTANCE, LEAD-EXPOSURE, PRECIPITATION
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Atatürk Üniversitesi Adresli:
Evet
Özet
Abstract
Austenitic stainless steels (SSs) are commonly used as in-core and surrounding structural materials in today’s industrial BWR and PWR systems. Such adaptable steels have also been the primary materials studied and used in several advanced nuclear reactor technologies, such as fast breeding and magnetic fusion reactors. In this study, some critical material properties, such as structural, physical, and radiation-shielding properties of REX-734 and 316L SS, were experimentally evaluated and compared to those of a number of other alloys. In addition to homogeneous element distribution, both alloys exhibit strong crystal orientation. The REX-734 alloy has a tensile strength of 1,259 MPa, whereas the 316L SS alloy has a tensile strength of 495 MPa. Moreover, nitrogen in the REX-734 alloy formed ultra-hard nitrides with Cr, Nb, and Si and precipitated into the structure and increased the strength. According to our findings, the mass attenuation coefficient values of the 316L SS sample were slightly higher than those of the REX-734 sample at all energies. It can be concluded that the REX-734 sample, with its exceptional strength qualities and excellent radiation attenuation capabilities, may be a viable nuclear power plant material for future investigations.