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Hidrojenin Zircaloy-4 Alaşımının Mekanik Davranışı Üzerindeki Etkisinin İncelenmesi
(Fen Bilimleri Enstitüsü, 2020)
Zirconium alloys are used as fuel cladding material in Light Water Reactors (LWR) and
act as the first barrier to fission product release by physically separating uranium oxide
fuel pellets and primary coolant.
During ...
Dinamik Monte Carlo Tekniği İle Zamana Bağlı Nükleer Reaktör Analizi
(Fen Bilimleri Enstitüsü, 2020-09-02)
In this study, a detailed non-analog Dynamic Monte Carlo (DMC) methodology is provided and used to investigate the transient analysis of nuclear systems. The validity of the given methodology is demonstrated by solving a ...
VVER-1200 Reaktöründe Soğutucu Kaybı Kazası ve Belirsizlik Analizi
(Fen Bilimleri Enstitüsü, 2020)
The objective of this thesis is to perform the thermal-hydraulic analysis of VVER-1200 reactor under Loss of Coolant Accident (LOCA) conditions including uncertainty calculations for the Peak Cladding Temperature (PCT) ...
Treat Reaktöründe Işınlanan Gelişmiş Metalik Alaşımların Radyasyon Hasarı Hesaplamaları
(Fen Bilimleri Enstitüsü, 2020)
The new generation reactor concepts that have been designed so far are foreseen for a common goal for safer, longer-lasting, nuclear non-proliferation and more economical use of nuclear energy. The most important issue to ...
Nükleer Tıpta Kullanılan Radyoizotopların Radyasyon Zırhlaması İçin Yazılım Geliştirilmesi
(Fen Bilimleri Enstitüsü, 2020-07-07)
In this study, a shielding software was developed in order to use in radiation shielding calculations of radioisotopes used in the Nuclear Medicine Departments of Hospitals in our country. Utilizing the software, it is ...
Kazaya Toleranslı ve Yüksek Yanma Oranlı Kullanılmış Yakıt İçin Kuru Depolama Kabı Analizi
(Fen Bilimleri Enstitüsü, 2021)
In this study, the analysis of a dry storage cask for accident-tolerant and high-burnup spent fuel was performed. For a dry storage cask design currently in use, in case of loading with the accident-tolerant fuel discharged ...
Kullanılmış Yakıttan Uranyum ve Plütonyumun Tam Birlikte Geri Kazanıldığı Yakıt Çevriminin Nükleer Silahsızlanma Açısından Değerlendirilmesi
(Fen Bilimleri Enstitüsü, 2021-07)
Spent nuclear fuel discharged from a typical LWR contains approximately 95 weight percent (w/o) uranium (U) and 0.5-1.0 w/o plutonium (Pu); the remainder consists of a small amount of fission products and minor actinides. ...
Pasif Nötron Doz Ölçüm Sistemlerinin Monte Carlo Yöntemi ile Benzeşimi
(Fen Bilimleri Enstitüsü, 2021)
The aim of this work is to make Monte Carlo simulations of two different CR-39 passive neutron dosimeter systems used to measure of personal dose equivalents of thermal and fast neutrons. Determination of fluence response ...
Sonlu Hacimler Yöntemi ile Kor Nötronik Analizi
(Fen Bilimleri Enstitüsü, 2021-12-27)
In this thesis, a code that can be used to perform 3 dimensional neutronics analysis of nuclear reactor cores is developed. The code discretizes two group neutron diffusion equations using finite volume method for the ...
Nükleer Santrallerin Yatırım Maliyetleri ve Yatırım Maliyetinin Seviyelendirilmiş Elektrik Maliyetine Etkisi
(Fen Bilimleri Enstitüsü, 2023)
The aim of this thesis is to assess different scenarios based on the factors affecting investment costs, which have the largest share in the unit cost (LCOE) of electricity produced from nuclear power plants, and the effects ...