Experimental investigation of radiation shielding performances of some important AISI-coded stainless steels: Part I

• Published in: Radiation physics and chemistry (Oxford, England : 1993) England : 1993), 2020-01, Vol.166, p.108455, Article 108455
• Main Authors: Alım, Bünyamin, Şakar, Erdem, Baltakesmez, Ali, Han, İbrahim, Sayyed, M.I., Demir, Lütfü
• Format: Article
• Language: English
• Subjects: Atomic properties; Attenuation coefficients; Austenitic stainless steels; Cesium 137; Cesium isotopes; Corrosion resistance; Cross-sections; Effective atomic number; Effective electron number; Ferritic stainless steel; Ferritic stainless steels; Mass attenuation coefficient; Mathematical analysis; Mechanical properties; Nickel; Parameters; Photons; Radiation shielding; Sodium 22; Stainless steels; Steel scrap
• ISSN: 0969-806X; 1879-0895
• DOI: 10.1016/j.radphyschem.2019.108455

The investigation of radiation shielding performances of AISI-302, 304, 321 and 430 stainless steels which have wide range of application because of their superior mechanical properties, temperature and corrosion resistances was aimed in this study. In accordance with this purpose, photon-shielding parameters of these stainless steels were calculated both experimentally and theoretically. These parameters calculated are linear attenuation coefficient, mass attenuation coefficient, mean free path, half-value layer, quarter-value layer, tenth-value layer, total atomic cross-section, total electronic cross-section, effective atomic number, effective electron number and effective conductivity. They were experimentally measured at twenty-three different energies in the range 22 keV and 1333 keV. The photon energies were obtained from seven different radioactive sources (22Na, 60Co, 241Am, 109Cd, 137Cs, 152Eu and 133Ba). The Si(Li) and NaI(Tl) detectors were separately used taking into account of energy-efficient regions to counting process at narrow-beam transmission geometry. In addition, all these parameters were computed at the 15 keV‒15 MeV wide energy range, theoretically. In order to make a satisfying assessment about radiation shielding capabilities of AISI 302, 304, 321 and 430 alloys, all calculations were also made for ordinary, steel-scrap and steel-magnetite concretes (Fe-based steel concretes) that are most commonly used as shielding material in many nuclear applications. According to the results obtained, it was observed that the radiation shielding performances of AISI 300 austenitic stainless steel series with containing Ni are superior to that of both AISI 430 ferritic stainless steel and examined concretes. •Austenitic stainless steels have unique radiation shielding features.•Stainless steels can be preferred as a shielding material in nuclear applications.•AISI-coded steels have better shielding capabilities than shielding concretes.•This study can guide to design of new materials for radiation applications.