Veli Çapali

Production Cross–Section Calculations of Medical 177Lu Using Neutron and Proton Induced Reactions

Abstract. In this study, we aimed to investigate the alternative ways to produce 177 Lu, an isotope which has a growing rate of usage in radionuclide therapy applications. For this purpose; we analyzed the 176 Lu (n,γ) 177 Lu, 176 Yb (n,γ) 177 Yb 177 Lu, 181 Ta (n,n+α) 177-M Lu, nat W(p,x) 177 Lu reactions with the TALYS 1.6 and EMPIRE 3.2 theoretical nuclear reaction codes. Obtained results with the TALYS 1.6 and EMPIRE 3.2 codes are also compared with the experimental data exists in the literature for each reaction. Keywords: 177 Lu, Cross–Section, TALYS 1.6, EMPIRE 3.2. Ozet. Bu calismada, radyonuklit terapi uygulamalarinda giderek artan bir kullanim oranina sahip olan 177 Lu izotopu icin alternatif uretim yollarinin arastirilmasi amaclanmistir. Bu amacla; 176 Lu(n,γ) 177 Lu, 176 Yb(n,γ) 177 Yb 177 Lu, 181 Ta(n,n+α) 177-M Lu, nat W(p,x) 177 Lu reaksiyonlari TALYS 1.6 ve EMPIRE 3.2 teorik nukleer reaksiyon kodlari kullanilarak analiz edilmistir. Ayrica, TALYS 1.6 ve EMPIRE 3.2 kodlari ile elde edilen bulgular her bir reaksiyon icin literaturde mevcut deneysel veriler ile karsilastirilmistir. Anahtar Kelimeler: 177 Lu, Tesir Kesiti, TALYS 1.6, EMPIRE 3.2.

Reaction Cross–Section Calculations for the Structural Reactor Materials 58,60,61,62,64Ni with Different Level Density Models

Abstract. In this study, reaction cross–section calculations of 58 Ni(d,n) 59 Cu, 60 Ni(d,n) 61 Cu, 60 Ni(d,2n) 60 Cu, 61 Ni(d,n) 62 Cu, 62 Ni(d,2n) 62 Cu, 64 Ni(d,2n) 64 Cu reactions have been done with TALYS 1.6, EMPIRE 3.1 and ALICE/ASH computation codes for reactor structural materials 58,60,61,62,64 Ni. Two Component Exciton and Equilibrium models of TALYS 1.6 and Exciton model of EMPIRE 3.1 have been used while Geometry Dependent Hybrid and Weisskopf Ewing models of ALICE/ASH have been selected for calculations. Also, by using Constant Temperature Fermi Gas, Back Shifted Fermi Gas and Generalized Superfluid models of TALYS 1.6, level density calculations for the selected reactions have been completed. All computations have been compared with the experimental values exist in the literature. Keywords : Reaction cross–section, Level density, GEANT4, Stopping power, Nickel, EXFOR Ozet. Bu calismada, 58 Ni(d,n) 59 Cu, 60 Ni(d,n) 61 Cu, 60 Ni(d,2n) 60 Cu, 61 Ni(d,n) 62 Cu, 62 Ni(d,2n) 62 Cu, 64 Ni(d,2n) 64 Cu reaksiyonlari icin TALYS 1.6, EMPIRE 3.1 ve ALICE/ASH hesaplama kodlari kullanilarak reaktor yapi malzemelerinden olan 58,60,61,62,64 Ni icin reaksiyon tesir kesiti hesaplamalari yapilmistir. TALYS 1.6’nin Iki Bilesenli Eksiton ve Denge modelleri ile EMPIRE 3.1’in Eksiton modelleri kullanilirken ALICE/ASH’in Geometri Bagimli Hibrit ve Weisskopf Ewing modelleri hesaplamalar icin secilmistir. Ayrica, TALYS 1.6’nin Sabit Sicaklik Fermi Gaz, Geri Kaymali Fermi Gaz ve Genellestirilmis Superakiskan modelleri ile seviye yogunlugu hesaplamalari secilen reaksiyonlar icin tamamlanmistir. Tum hesaplamalar, literaturde mevcut olan deneysel degerler ile karsilastirilmistir. Anahtar Kelimeler : Reaksiyon tesir kesiti, Seviye yogunlugu, GEANT4, Durdurma gucu, Nikel, EXFOR

Nurse exposure doses resulted from bone scintigraphy patient

Bone scintigraphy is used for displaying the radiologic undiagnosed bone lesions in nuclear medicine. It’s general indications are researching bone metastases, detection of radiographically occult fractures, staging and follow-up in primary bone tumors, diagnosis of paget’s disease, investigation of loosening and infection in orthopedic implants. It is applied with using 99mTc labeled radiopharmaceuticals (e.g 99m Tc MDP,99mTc HEDP and 99mTc HMDP). 20 -25 mCi IV radiotracer was injected into vein and radiotracer emits gamma radiation. Patient waits in isolated room for about 3 hours then a gamma camera scans radiation area and creates an image. When some patient’s situation is not good, patients are hospitalized until the scanning because of patients’ close contact care need. In this study, measurements were taken from ten patients using Geiger Muller counter. After these measurements, we calculated nurse’s exposure radiations from patient’s routine treatment, examination and emergency station.

Production cross–section calculations of medical 32P, 117Sn, 153Sm and 186,188Re radionuclides used in bone pain palliation treatment

Abstract In this study, production cross–section calculations of 32P, 117Sn, 153Sm and 186,188Re radionuclides used in bone pain palliation treatment produced by 30Si(d,γ)32P, 118Sn(γ,n)117Sn, 116Sn(n,γ)117Sn, 150Nd(α,n)153Sm, 154Sm(n,2n)153Sm, 152Sm(n,γ)153Sm, 186W(d,2n)186Re, 187Re(γ,n)186Re, 185Re(n,γ)186Re and 187Re(n,γ)188Re reactions have been investigated in the different incident energy range of 0.003–34 MeV. Two-component exciton and generalised superfluid models of the TALYS 1.6 and exciton and generalised superfluid models of the EMPIRE 3.1 computer codes have been used to pre-equilibrium (PEQ) reaction calculations. The calculated production cross–section results have been compared with available experimental results existing in the experimental nuclear reaction database (EXFOR). Except the 118Sn(γ,n)117Sn, 150Nd(α,n)153Sm and 185Re(n,γ)186Re reactions, the two-component exciton model calculations of TALYS 1.6 code exhibit generally good agreement with the experimental measurements for all reactions used in this present study.