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  • MakaleYalnız künye2023Scopus SJRQ1
    Gamma-ray and neutron shielding capability of blended cement-stabilized barite fillers developed by maximum density method

    Gökçe, H.S.; Öksüzer, N.; Kamiloğlu, H.A.; Yılmaz, F.

    The disposal of radiological wastes in the deep geological repositories has become an important issue for the reduction of hazardous risks on the human and biological environments. In this study, blended cement-stabilized barite fillers against gamma rays and neutrons have been developed with the use of the maximum density method by considering various amounts of water (100–300 kg/m3), binder (4–10%), and compaction energy (500–2000 kJ/m3). According to the experimental series of these filler materials, satisfactory response surface results have been achieved in the study. The experimental results revealed that compacted filling material can ensure an efficient shielding capability for gamma rays and neutrons when designed with a density of 3.064 g/cm3. An increase in binder content, water content, and compaction energy has improved the compressive strength of these materials up to 37 times according to that of the poorest series. Neutron and gamma-ray shielding capabilities were found to be 119 and 14% higher than those of the poorest filler material, respectively when theoretical and experimental results are considered in the study.

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  • MakaleAçık Erişim2023Scopus SJRQ1
    An extensive survey on radiation protection features of novel hafnium iron-borophosphate glasses: Experimental and theoretical study

    Şakar, Erdem; Alım, Bünyamin; Ertap, Hüseyin; Karabulut, Mevlut

    This study aimed to determine the radiation (photon and particle) attenuation abilities of Hf added iron-borophosphate glasses considered as a candidate host matrix for Pu containing nuclear waste. Experimental absorption parameters were measured using 133Ba radionuclide for photon radiation, and the same parameters were theoretically calculated using Phy-X/PSD. The obtained data were evaluated comparatively for all glasses depending on the Hf and B contents. It has been determined that all of the glasses examined have photon absorption ability at a level that can be a shielding material for nuclear applications. In addition, the interaction cross-sections with particle radiations were computed using SRIM and ESTAR software. When the data obtained are evaluated thoroughly, it can be said that investigated glasses can be used as shielding in areas that require protection from both photon and particle radiation, in addition to being a candidate material for the vitrification of nuclear wastes containing Pu.

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Tam Kayıt
AlanDeğerDil
creativeworkseries.issn0149-1970
dc.date.accessioned2026-10-29T19:08:39.656851063Z
dc.date.available2026-10-29T19:08:39.656851063Z
dc.identifier.urihttps://rdlopen.rawdatalibrary.net/r/bayburt/11671
dc.publisherElsevier Ltd
dc.rightsinfo:eu-repo/semantics/openAccess
dc.titleProgress in Nuclear Energy