Results from performed calculations were compared with the experimental nuclear reaction data exist in EXFOR.
📌 3 Key Takeaways
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Objective & Hypothesis:BeO is one of the most common moderator material for neutron moderation; due to its high density, neutron capture cross section and physical-chemical properties that provides usage at elevated temperatures.
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Key Findings & Data:The cross–sections of (n,α), (n,2n), (n,t), (n,EL) and (n,TOT) reactions for 9Be and 16O nuclei have been calculated by using TALYS 1.6 Two Component Exciton model and EMPIRE 3.2 Exciton model in this study.
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Conclusion & Impact:Results from performed calculations were compared with the experimental nuclear reaction data exist in EXFOR.
BeO is one of the most common moderator material for neutron moderation; due to its high density, neutron capture cross section and physical-chemical properties that provides usage at elevated temperatures. As it’s known, for various applications in the field of reactor design and neutron capture, reaction cross–section data are required. The cross–sections of (n,α), (n,2n), (n,t), (n,EL) and (n,TOT) reactions for 9Be and 16O nuclei have been calculated by using TALYS 1.6 Two Component Exciton model and EMPIRE 3.2 Exciton model in this study. Hadronic interactions of low energetic neutrons and generated isotopes–particles have been investigated for a situation in which BeO was used as a neutron moderator by using GEANT4, which is a powerful simulation software. In addition, energy deposition along BeO material has been obtained. Results from performed calculations were compared with the experimental nuclear reaction data exist in EXFOR.
ÇAPALI, V., ŞEKERCİ, M., ÖZDOĞAN, H., KAPLAN, A. (2016). Reaction Cross Section Calculations in Neutron Induced Reactions and GEANT4 Simulation of Hadronic Interactions for the Reactor Moderator Material BeO. Süleyman Demirel Üniversitesi Fen Bilimleri Enstitüsü Dergisi, Cilt: 20 - Sayı: 2, 161–166. https://ajindex.com/articles/310176
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