| Yazarlar |
Dr. Öğr. Üyesi Murat DAĞ
Kırşehir Ahi Evran Üniversitesi, Türkiye |
| Özet |
| Selection of the appropriate materials as a structural components of nuclear reactor are of key importance to implement thehighest efficiency and security. Zr, Fe, Cr, Sn and Nb are commonly used materials involved in structural alloy inside thereactor. The presented result of neutron-induced reaction cross section calculations for 50-52-53-54Cr, 54-56-57Fe,93Nb, 117Sn, 90-91-92Zr have been computed using Constant Temperature Model, Back Shifted Fermi Gas Model, Generalised Super FluidModel and Microscopic level densities presented in TALYS 1.9 nuclear code. The calculations have been repeated bychanging the level density parameter a for each isotope and model to observe changes in the model assumption. The obtainedresults are compared with the experimental data taken from the literature. |
| Anahtar Kelimeler |
| Makale Türü | Özgün Makale |
| Makale Alt Türü | Ulusal alan endekslerinde (TR Dizin, ULAKBİM) yayımlanan tam makale |
| 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 |
| Doi Numarası | 10.18038/estubtda.831556 |
| Makale Linki | http://dx.doi.org/10.18038/estubtda.831556 |
| Atıf Sayıları |
