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

Yıl 2021, , 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

• Blann, M. (1971). Hybrid model for pre-equilibrium decay in nuclear reactions. Physical Review Letters, 27(6), 337–340. doi:10.1103/PhysRevLett.27.337
• Blann, M. (1996). New precompound decay model. Physical Review C - Nuclear Physics, 54(3), 1341–1349. doi:10.1103/PhysRevC.54.1341
• Blann, M. (2011). Particle Spectra from HMS Precompound Nucleus Decay (ALICE2011). Package ID USCD1238, 5.
• Capote, R., Osorio, V., Lopez, R., Herrera, E., & Piris, M. (1991). Analysis of Experimental Data on Neutron-Induced Reactions and Development of Code PCROSS for The Calculation of Differential Pre-equilibrium Emission Spectra With Modelling of Level Density Function.
• Clement Lemaignan (2010). Nuclear Materials and Irradiation Effects. Dan Gabriel Cacuci (Ed.), Handbook of Nuclear Engineering (545-631). Boston, MA, USA: Springer. doi:10.1007/978-0-387-98149-9
• Fynan, D. A., Seo, Y., Kim, G., Barros, S., & Kim, M. J. (2021). Photoneutron production in heavy water reactor fuel lattice from accelerator-driven bremsstrahlung. Annals of Nuclear Energy, 155, 108141. doi:10.1016/j.anucene.2021.108141
• Griffin, J. J. (1966). Statistical model of intermediate structure. Physical Review Letters, 17(9), 478–481.doi:10.1103/PhysRevLett.17.478
• Gudima, K. K., Mashnik, S. G., & Toneev, V. D. (1983). Cascade-exciton model of nuclear reactions. Nuclear Physics, Section A, 401(2), 329–361. doi:10.1016/0375-9474(83)90532-8
• Gupta, C. K. (2001). Nuclear Reactor Materials. In K.H. J. Buschow, R. W. Cahn, M. C. Flemings, B. Ilschner, E. J. Kramer, S. Mahajan, P. Veyssière (Eds.), Encyclopedia of Materials: Science and Technology (pp. 6339–6349). Pergamon. doi:10.1016/B0-08-043152-6/01123-2
• IAEA. (2000). Handbook on Photonuclear Data for Applications Cross-sections and Spectra. 7, 284. http://www-pub.iaea.org/books/IAEABooks/6043/Handbook-on-Photonuclear-Data-for-Applications-Cross-sections-and-SpectraMashnik, S. G., Gudima, K. K., Sierk, A. J., Baznat, M. I., & Mokhov, N. V. (2005). CEM03. 01 user manual. LANL Report LA UR, 5, 7321.
• NEA (2015). JANIS 4.0 Java-based Nuclear Data Information System. https://www.oecd-nea.org/janis/. Erişim tarihi: 25.03.2021.
• Özdoğan, H., Şekerci, M., & Kaplan, A. (2020). An Investigation on the Effects of Some Theoretical Models in the Cross-Section Calculations of 50,52,53,54Cr(alpha,x) Reactions. Physics of Atomic Nuclei, 83(6), 820–827. doi:10.1134/s1063778820660060
• Pearton, S. J., Deist, R., Ren, F., Liu, L., Polyakov, A. Y., & Kim, J. (2013). Review of radiation damage in GaN-based materials and devices. Journal of Vacuum Science & Technology A: Vacuum, Surfaces, and Films, 31(5), 050801. doi:10.1116/1.4799504
• Shultis, J. K., & Faw, R. E. (2010). Radiation Shielding and Radiological Protection, v.2. In D. G. Cacuci (Eds.), Handbook of Nuclear Enginering (pp. 1313-1448). Boston, MA,USA: Springer. doi:10.1007/978-0-387-98149-9_11.
• Shultis, J. K., & Faw, R. E. (2012). Radiation Shielding. In R. A. Meyers (Eds.), Encyclopedia of Sustainability Science and Technology (pp. 8536-8559). Newyork, USA: Springer-Verlag New York. doi:10.1007/978-1-4419-0851-3_25
• Siddik, T. (2019). Theoretical cross-sectional calculation of some structural fusion material on (n, α)-induced reactions. Indian Journal of Physics, 93(7), 921–925. doi:10.1007/s12648-018-1349-3
• Simnad, M. T. (2003). Nuclear Reactor Materials and Fuels. In R. A. Meyers (Eds.), Encyclopedia of Physical Science and Technology (Third Edition) (pp. 775–815). USA: Academic Press. doi:10.1016/b0-12-227410-5/00498-1
• Uǧur, F. A., Tel, E., & Gökçe, A. A. (2013). A study on 19F(n,α) reaction cross section. Journal of Fusion Energy, 32(3), 414–418. doi:10.1007/s10894-012-9587-4
• Weisskopf, V. F., & Ewing, D. H. (1940). On the yield of nuclear reactions with heavy elements. Physical Review, 57(6), 472–485. doi:10.1103/PhysRev.57.472