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Journals / Süleyman Demirel Üniversitesi Fen Edebiyat Fakültesi Fen Dergisi / 2026 / Volume: 14 Issue: 1

Calculation of Production Reaction Cross Section of Some Radiopharmaceuticals Used in Nuclear Medicine by New Density Dependent Parameters

Nükleer Tıpta Kullanılan Bazı Radyofarmasötiklerin Üretim Reaksiyon Tesir Kesitlerinin Yoğunluğa Bağlı Yeni Parametrelerle Hesaplanması

Yusuf Kavun(KAHRAMANMARAŞ SÜTÇÜ İMAM ÜNİVERSİTESİ, KAHRAMANMARAŞ SAĞLIK HİZMETLERİ MESLEK YÜKSEKOKULU)0000-0001-9635-4388
Eyyup Tel(Osmaniye Korkut Ata Üniversitesi Fen Edebiyat Fakültesi Fizik Bölümü)0000-0002-5422-3301
Muhittin Şahan(Osmaniye Korkut Ata Üniversitesi Fen Edebiyat Fakültesi Fizik Bölümü)0000-0001-6716-8463
Ahmet Salan(KAHRAMANMARAŞ SÜTÇÜ İMAM ÜNİVERSİTESİ)0000-0002-5022-1851
Pages
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Publication Date
2019-05-31
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AI Summary & Key Takeaways

AI Insight
⚡ TL;DR(Too Long; Didn't Read)

While the calculated value from the semi-empirical formula developed by Tel et al. (2008) gave reasonable results, the density-dependent calculations were observed lower values than that of experimental values.

📌 3 Key Takeaways

🎯
Objective & Hypothesis:In nuclear medicine, radiopharmaceuticals are used for diagnosis or treatment purposes.
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Key Findings & Data:In this study, the production reaction cross sections were calculated for two selected radiopharmaceutical nuclei ( 99 Tc and 115 In) using the semi-empirical cross section formula for the ( n, α ) reactions developed by Tel et al. (2008).
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Conclusion & Impact:While the calculated value from the semi-empirical formula developed by Tel et al. (2008) gave reasonable results, the density-dependent calculations were observed lower values than that of experimental values.
🔬Design:Research Article
📍Scope:2008 Verileri
⚙️Variables:Nuclear medicine · Nuclear reactions · Cross section

Abstract

In nuclear medicine, radiopharmaceuticals are used for diagnosis or treatment purposes. Radiopharmaceuticals containing radionuclide in their structure are produced by reactors, generators or cyclotrons and are generally used for scintigraphy or tomographic investigations. The produced radionuclides can be given to the human body together with organic or inorganic substances. In this study, the production reaction cross sections were calculated for two selected radiopharmaceutical nuclei ( 99 Tc and 115 In) using the semi-empirical cross section formula for the ( n, α ) reactions developed by Tel et al. (2008). The density depending on (n, α) reaction cross sections were also investigated with the four Skyrme Hartree Fock parameters (S3, T3, SKM and SKM*). While the calculated value from the semi-empirical formula developed by Tel et al. (2008) gave reasonable results, the density-dependent calculations were observed lower values than that of experimental values.

Özet

Nükleer tıpta, radyofarmasötikler tanı veya tedavi amacıyla kullanılmaktadır. Yapılarında radyonüklid içeren radyofarmasötikler, reaktör, jeneratör veya siklotronlarla üretilirler ve genellikle sintigrafik veya tomografik incelemelerde kullanılır. Üretilen radyonüklidler, organik veya inorganik maddelerle birlikte vücuda verilebilir. Bu çalışmada, (n, α) reaksiyonları için Tel ve arkadaşları (2008) tarafından geliştirilen yarı-ampirik tesir kesit formülü kullanılarak seçilen iki radyofarmasötik çekirdek ( 99 Tc ve 115 In) için üretim reaksiyonu tesir kesitleri hesaplanmıştır. Ayrıca, yoğunluğa bağlı ampirik (n, α) (2008) nükleer reaksiyon tesir kesitleri dört Skyrme Hartree Fock parametreleri (S3, T3, SKM ve SKM*) kullanılarak da incelenmiştir. Tel ve ark. (2008) tarafından geliştirilen yarı ampirik formülünden hesaplanan değer uyumlu çıkarken, yoğunluğa bağlı hesaplamaların deneysel değerlerden daha aşağıda olduğu gözlemlenmiştir.

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Cite This Article

Kavun, Y., Tel, E., Şahan, M., Salan, A., *, Y. K. (2019). Calculation of Production Reaction Cross Section of Some Radiopharmaceuticals Used in Nuclear Medicine by New Density Dependent Parameters. Süleyman Demirel Üniversitesi Fen Edebiyat Fakültesi Fen Dergisi, Volume: 14 Issue: 1. https://doi.org/10.29233/sdufeffd.477539

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