Eriyik Tuz Reaktörlerinde Yakıt Malzemesi Olarak Kullanılan Na Çekirdeğinin Üretim Tesir Kesiti Hesaplamaları

Abstract

In this study, the production cross sections of Na nucleus used as fuel material in molten salt reactors have been calculated. The calculations for 24Mg(p,α)21Na, 23Na(n,γ)24Na,24Mg(n,p)24Na,Ne(d,n)21Na and23Na(n,2n)22Na reactions have been carried out up to 70 MeV incident particle energies by using the equilibrium and pre–equilibrium nuclear reaction models. Full Exciton Model, Hybrid Model, Geometry Dependent Hybrid Model and Cascade Exciton Model for the pre–equilibrium reactions and Weisskopf–Ewing Model for the equilibrium reactions have been used. The calculated results have been compared with experimental data taken from the Experimental Nuclear Reaction Data (EXFOR) library. Also, the optimum energy ranges for 21,22,24Na production have been determined

Keywords

• Molten salt reactor, reaction cross section, EXFOR, equilibrium and pre–equilibrium reactions, nuclear reaction models

Eriyik Tuz Reaktörlerinde Yakıt Malzemesi Olarak Kullanılan Na Çekirdeğinin Üretim Tesir Kesiti Hesaplamaları

Abstract

Özet: Bu çalışmada, eriyik tuz reaktörlerinde yakıt malzemesi olarak kullanılan Na çekirdeğinin üretim tesir kesitleri hesaplanmıştır. Hesaplamalar; 24Mg(p,α)21Na, 23Na(n,γ)24Na, 24Mg(n,p)24Na, 20Ne(d,n)21Na ve 23Na(n,2n)22Na reaksiyonları için 70 MeV parçacık gelme enerjisine kadar denge ve denge–öncesi nükleer reaksiyon modelleri kullanılarak gerçekleştirilmiştir. Denge–öncesi hesaplamalar için; Full Exciton Model, Hibrit Model, Geometri Bağımlı Hibrit Model ve Cascade Exciton Model, denge hesaplamaları için ise; Weisskopf–Ewing Model kullanılmıştır. Elde edilen sonuçlar, Deneysel Nükleer Reaksiyon Data (EXFOR) Kütüphanesi'nden alınan deneysel değerlerle karşılaştırılmıştır. Ayrıca; 21,22,24Na üretimi için optimum enerji aralıkları belirlenmiştir. Anahtar kelimeler: Eriyik tuz reaktörleri, reaksiyon tesir kesiti, EXFOR, denge ve denge–öncesi reaksiyonlar, nükleer reaksiyonlar modelleri Production Cross Section Calculations of Na Nucleus Used as Fuel Material in Molten Salt Reactors Abstract: In this study, the production cross sections of Na nucleus used as fuel material in molten salt reactors have been calculated. The calculations for 24Mg(p,α)21Na, 23Na(n,γ)24Na, 24Mg(n,p)24Na, 20Ne(d,n)21Na and 23Na(n,2n)22Na reactions have been carried out up to 70 MeV incident particle energies by using the equilibrium and pre–equilibrium nuclear reaction models. Full Exciton Model, Hybrid Model, Geometry Dependent Hybrid Model and Cascade Exciton Model for the pre–equilibrium reactions and Weisskopf–Ewing Model for the equilibrium reactions have been used. The calculated results have been compared with experimental data taken from the Experimental Nuclear Reaction Data (EXFOR) library. Also, the optimum energy ranges for 21,22,24Na production have been determined. Key words: Molten salt reactor, reaction cross section, EXFOR, equilibrium and pre–equilibrium reactions, nuclear reaction models

Keywords

• Eriyik tuz reaktörleri, reaksiyon tesir kesiti, EXFOR, denge ve denge–öncesi reaksiyonlar, nükleer reaksiyonlar modelleri

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14. Veli ÇAPALI e-posta :[e-mail]
15. Hasan ÖZDOĞAN e-posta : [e-mail]
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