Neutronic Calculations at Uraniım Powered Cylindrical Reactor by Usıng Bessel Dıfferentıal Equation. (Nuclear Science and TECHNOLOGY)
Yazarlar (1)
Prof. Dr. Aybaba HANÇERLİOĞULLARI Kastamonu Üniversitesi, Türkiye
| Bölüm Adı | Neutronic Calculations at Uraniım Powered Cylindrical Reactor by Usıng Bessel Dıfferentıal Equation. | ||
| Kitap Adı | Nuclear Science and TECHNOLOGY | ||
| Bölüm Sayfaları | 15-24 | ||
| Kitap Türü | Kitap Bölümü | ||
| Kitap Alt Türü | Alanında uluslararası yayınlanan kitap bölümü | ||
| Kitap Niteliği | Diğer uluslararası bilimsel kitap | ||
| Kitap Dili | İngilizce | Basım Tarihi | 01-2012 |
| DOI Numarası | – | ISBN | 978-81-8795-546-9 |
| Basıldığı Ülke | Basıldığı Şehir | ||
| UAK Araştırma Alanları |
Nükleer Fizik
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| Özet |
| Nuclear reactors are the complex machine-equipment systems constructed through the use of advanced engineering technologies. Fission-type reactors are devices developed to generate energy at a stable power by taking the chain reaction under control. Therefore, K, neutron multiplication coefficient is an important nuclear parameter for a nuclear reactor to sustain generating energy by itself at a stable power. K, is the ratio of the number of neutrons generated in a generation to the number of neutrons absorbed in the previous generation. In this study, It has been used different cylindrical fuel configurations. These configurations are Uranium isotopes (% 98, 13 233U,% 1, 24 234U,% 0, 03235U,% 0, 60238U), respectively. For these configurations it has been calculated criticality (KEFF) using Bessel differential equation, Neutron flux (Ø) averaged over cylindrical surface and total fission energy deposition over cylindrical can be applied. The Bessel equation is formulated as follows and this equation is a special case of Bessel’s equation [1, 2]. |
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