| Yazarlar (8) |
Prof. Dr. Aybaba HANÇERLİOĞULLARI
Kastamonu Üniversitesi, Türkiye |
Prof. Dr. Aslı KURNAZ
Kastamonu Üniversitesi, Türkiye |
Yosef G Ali Madee
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Ltfeı Abdalsmd
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Salem A A Shufat
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Kaled Mohamed El Hadad
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Hend Hadıa Almazogi
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Mansur Mohamed Ali
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| Özet |
| In this study, based differential equations methods are used to solve equations because these methods are dependent on boundary value data more than other mathematical equations. We have calculated neutron flux, criticality and geometrical eigenvalue by using multi-group method and solving the neutron diffusion equation for finite and infinite cylindrical and spherical reactors in this study. For the calculation of the total neutron flux cross sections, we need the neutron diffusion equation. Thus, we have established the relationship between neuron flow and cross-section of neuron depending on neutron energy. Critical calculations have been made by comparing the results with MNCP (montecarlo n-partical) simulation methods. For necessary computer calculations, the programme, Wolfram-Matematica-7 has been used. |
| Anahtar Kelimeler |
| Makale Türü | Özgün Makale |
| Makale Alt Türü | Uluslararası alan indekslerindeki dergilerde yayınlanan tam makale |
| Dergi Adı | Open Journal of Applied Sciences |
| Dergi ISSN | 2165-391 |
| Dergi Tarandığı Indeksler | ISI WEB OF KNOW LEDGE |
| Makale Dili | İngilizce |
| Basım Tarihi | 01-2017 |
| Cilt No | 7 |
| Sayfalar | 68 / 81 |
