Analysis of neutron capture cross section using different level density models on cadmium isotopes up to 250 keV neutron-induced energy and GEANT4 simulation von Çapalı, Veli

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Gamma radiation exposure of accompanying persons due to Lu-177 patients von Kovan, Bilal, Demir, Bayram, Tuncman, Duygu, Capali, Veli, Turkmen, Cuneyt

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Geant4 calculations for space radiation shielding material Al2O3 von Capali, Veli, Tolga Acar Yesil, Kaya, Gokhan, Kaplan, Abdullah, Yavuz, Mustafa, Tilki, Tahir

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Fission cross section calculations for 209 Bi target nucleus based on fission reaction models in high energy regions von Kaplan, Abdullah, Capali, Veli, Ozdogan, Hasan

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Fission cross section calculations for super(209)Bi target nucleus based on fission reaction models in high energy regions von Kaplan, Abdullah, Capali, Veli, Ozdogan, Hasan

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Geant4 calculations for space radiation shielding material Al 2 O 3 von Capali, Veli, Yesil, Tolga Acar, Kaya, Gokhan, Kaplan, Abdullah, Yavuz, Mustafa, Tilki, Tahir

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Improve or Approximation of Nuclear Reaction Cross Section Data Using Artificial Neural Network von Capali, Veli

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OTR Sistemlerinde Silikon Görüntüleme Ekranın Geant4 Simülasyonu von Veli Çapalı, Suat Özkorucuklu

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Production Cross–Section Calculations of Medical125I Radionuclide Using α, d and γ Induced Reactions von Bayram DEMİR, Veli ÇAPALI, İsmail SARPÜN, Abdullah KAPLAN

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Eriyik Tuz Reaktörlerinde Yakıt Malzemesi Olarak Kullanılan Na Çekirdeğinin Üretim Tesir Kesiti Hesaplamaları von S. Sedat DOĞAN, Veli ÇAPALI, Hasan ÖZDOĞAN, Abdullah KAPLAN

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27 Al, 54 Fe, 58 Ni ve 90 Zr Hedef Çekirdekleri İçin 10–30 MeV Enerji Aralığında (γ,p) Reaksiyon Tesir Kesiti Hesaplamaları von Veli ÇAPALI, Hasan ÖZDOĞAN, S. Sedat DOĞAN, Abdullah KAPLAN

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