Yazar "Tonguc, Baris T." seçeneğine göre listele

Listeleniyor 1 - 2 / 2
  • Küçük Resim Yok
    Öğe
    Comprehensive evaluation of Epoxy/Li2B4O7 composite for neutron shielding: Experimental characterization and Geant4 simulation analysis
    (Pergamon-Elsevier Science Ltd, 2026) Abady, R. S.; Amro, B. M. S.; Saleh, H.; Alwaheba, Anas; Esaifan, Muayad; Arslan, Halil; Tonguc, Baris T.
    Epoxy-based composites were prepared by incorporating Li2B4O7 at concentrations ranging from 5 to 30 wt% to enhance neutron shielding performance. To assess the structure, morphology, and particle distribution within the epoxy matrix, scanning electron microscopy (SEM) was used. Experimental measurements with a(252)Cf neutron source at the Jordan Atomic Energy Commission revealed that the composite containing 15 wt% Li2B4O7 exhibited uniform particle distribution and achieved a 20 % improvement in neutron attenuation compared with pure epoxy. Notably, the experimental findings were consistent with Geant4 simulations, thus confirming and validating the simulation model. Furthermore, theoretical and simulation studies indicated that the incorporation of Li2B4O7 improved thermal neutron shielding by similar to 89 % and fast neutron shielding by similar to 8 %, while also reducing the average energy of secondary gamma radiation. Collectively, these results highlight the strong potential of Epoxy/Li2B4O7 composites for advanced neutron shielding applications, including their use as lightweight shielding layers or blocks in neutron facilities, as well as compact shipping containers with superior efficiency compared to conventional materials.
  • Küçük Resim Yok
    Öğe
    Theoretical modeling of 65Zn production via charged particle reactions on 66Zn
    (Pergamon-Elsevier Science Ltd, 2026) Alafeshat, Shatha; Arslan, Halil; Tonguc, Baris T.
    This study presents a comprehensive theoretical investigation into the production of the medically and industrially relevant radionuclide 65Zn via the 66Zn (p, pn)65Zn, 66Zn (d, t)65Zn and 66Zn (alpha, alpha n)65Zn reactions. A combination of Monte Carlo transport simulations (Geant4 toolkit and SRIM module) and nuclear reaction modeling (TALYS-2.0) was employed to evaluate the reaction mechanisms, excitation functions, and production yields. Stopping powers and penetration ranges of incident projectiles (proton, deuteron, alpha particle) in 66Zn were calculated using Geant4 and SRIM, showing strong mutual agreement. Excitation functions were simulated using both Geant4's hadronic physics models and TALYS-2.0, incorporating various optical model potentials and nuclear level density (NLD) formulations. Theoretical yields of 65Zn were determined for each reaction pathway, highlighting a marked improvement in production efficiency with increasing 66Zn isotopic enrichment. Geant4 was also utilized to assess the impact of target thickness on cross-section behavior, while final activation values and end-of-bombardment (EOB) activities were estimated for each reaction under standardized irradiation conditions. Among the investigated channels, the 66Zn (p, pn)65Zn reaction demonstrated the highest production yield and activity, confirming it as the most effective route for 65Zn generation within the examined energy range.