Investigation of Neutron-Induced Reaction Cross Sections for Several Nuclear Reactor Structural Materials
Yazarlar (1)
Dr. Öğr. Üyesi Murat DAĞ Kırşehir Ahi Evran Üniversitesi, Türkiye
| Makale Türü |
Özgün Makale
(Ulusal alan endekslerinde (TR Dizin, ULAKBİM) yayınlanan tam makale)
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| Dergi Adı | Eskişehir Technical University Journal of Science and Technology A - Applied Sciences and Engineering | ||
| Dergi ISSN | 2667-4211 | ||
| Dergi Tarandığı Indeksler | TR DİZİN | ||
| Makale Dili | Türkçe | Basım Tarihi | 01-2021 |
| Cilt / Sayı / Sayfa | 22 / 2 / 215–238 | DOI | 10.18038/estubtda.831556 |
| Makale Linki | http://dx.doi.org/10.18038/estubtda.831556 | ||
| UAK Araştırma Alanları |
Nükleer Fizik
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| Özet |
| Selection of the appropriate materials as a structural components of nuclear reactor are of key importance to implement the highest efficiency and security. Zr, Fe, Cr, Sn and Nb are commonly used materials involved in structural alloy inside the reactor. The presented result of neutron-induced reaction cross section calculations for Cr50-52-53-54, Fe54-56-57, Nb93, Sn117-119-124, Zr90-91-92 have been computed using Constant Temperature Model, Back Shifted Fermi Gas Model, Generalised Super Fluid Model and Microscopic level densities presented in TALYS 1.9 nuclear code. The calculations have been repeated by changing the level density parameter a for each isotope and model to observe changes in the model assumption. The obtained results are compared with the experimental data taken from the literature. |
| Anahtar Kelimeler |
BM Sürdürülebilir Kalkınma Amaçları
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| Google Scholar | 1 |