Reaktör Yapı Materyallerinde Bulunan Sc45, V51, Cr52, Co59 ve Cu63 İzotoplarının (γ,n) Reaksiyon Tesir Kesitleri Hesaplamaları

Yıl 2021, Cilt: 26 Sayı: 2, 61 - 68, 31.08.2021

Ömer Faruk Özdemir , Ali Arasoğlu

https://doi.org/10.53433/yyufbed.913870

Öz

Bu çalışmada reaktör korunda veya zırhlama betonunda kullanılan yapı malzemelerin de bulunan 45Sc, 51V, 52Cr, 59Co ve 63Cu izotoplarının, 10 - 50 MeV enerji aralığında foto - nötron reaksiyonlarının tesir kesiti hesaplamaları yapıldı. Hesaplamalarda Weisskopf - Ewing Model için PCROSS, Hibrid Monte - Carlo Simülasyon Modeli için ALICE - 2011 ve Kaskad Eksiton Model için de CEM03.01 programları kullanıldı. Her model için yapılan tesir kesiti hesaplamaları birbirleriyle, EXFOR (Experimental Nuclear Reaction Data) veri tabanından alınan deneysel veriler ile ve literatürde yer alan JANIS (Java - based Nuclear Information Software) veri kütüphanesinden elde edilen değerlendirilmiş verilerle (JENDL/PD - 2004 ve TENDL - 2014) karşılaştırıldı.

Anahtar Kelimeler

Foto-nötron reaksiyonları, Tesir kesiti, Denge modelleri, Denge öncesi modelleri

Destekleyen Kurum

YYÜ Bilimsel Araştırma Projeleri Başkanlığı

Proje Numarası

2013-FBE-D005

(γ,n) Reaction Cross Section Calculations of 45Sc, 51V, 52Cr, 59Co and 63Cu Isotopes in Reactor Building Materials

Öz

In this study, the cross - section calculations of photo - neutron reactions of 45Sc, 51V, 52Cr, 59Co and 63Cu isotopes which are used in building materials of reactor core or shielding concrete in the range of 10 - 50 MeV were performed. PCROSS for the Weisskopf - Ewing Model, ALICE - 2011 for the Hybrid Monte - Carlo Simulation Model, and CEM03.01 for the Cascade Exciton Model were performed in the calculations. The findings obtained from cross - section calculations of each model were compared not only with each other, but also experimental and theratical data gattehred from EXFOR (Experimental Nuclear Reaction Data) database and JANIS (Java - based Nuclear Information Software) data library (JENDL / PD - 2004 and TENDL - 2014), respectively.

Proje Numarası

2013-FBE-D005

Kaynakça

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