Dosya Biçimi"Yok" Nükleer Enerji Mühendisliği Bölümü için listeleme
Toplam kayıt 16, listelenen: 1-16
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Computational Fluid Dynamics (CFD) Modeling of Interfacial Momentum Transfer in Bubbly Two-Phase Flow
(Fen Bilimleri Enstitüsü, 2024)This dissertation addresses critical gaps in Computational Fluid Dynamics (CFD) modeling of momentum transfer in two-phase flow systems. Available models, based on empirical relations from the behavior of single bubbles ... -
Demo Füzyon Reaktörlerinde Üretim Battaniyesi Tasarımı
(Nükleer Bilimler Enstitüsü, 2024)Tritium, which serves as fuel in DEMO-type nuclear fusion reactors, is known to occur in trace amounts in nature. The aim of this study is to investigate the tritium production rate in the breeding blanket of DEMO-type ... -
Dijital Çakışma Sayım Yönteminin Geliştirilmesi ve 4pi-Beta-Gama Sayım Sisteminde Karmaşık Bozunma Şemalı Belirli Radyoizotoplara Uygulanması
(Fen Bilimleri Enstitüsü, 2019)The methods of data acquiring and processing in the 4πβ-γ coincidence counting systems for radionuclide standardization have been employed by using analogue electronic modules for decades. Since the supply and maintenance ... -
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 ... -
Ergimiş Tuz Toryum Reaktörleri İçin Kor Parametrelerinin ve Yakıt Çevrim Senaryolarının İncelenmesi
(Fen Bilimleri Enstitüsü, 2024-09-06)In the context of the thesis presented, scenarios for fuel cycles containing Thorium (Th) have been investigated for Molten Salt Reactors (MSRs), proposed as one of the Generation IV nuclear reactor types. Initially, an ... -
Ge Dedektörünün Zamana Bağlı Monte Carlo Yöntemi ve Genetik Algoritma ile Gerçekçi Modellenmesi
(Fen Bilimleri Enstitüsü, 2023)Simulation of radiation detectors using the Monte Carlo method is extensively utilized for various purposes such as obtaining detector efficiencies for primary activity measurements, transferring values obtained from ... -
Hafif Sulu Üretken Reaktör için Nötronik Analiz
(Fen Bilimleri Enstitüsü, 2023-01)The main objective of this study is to perform the neutronic analysis of the Light Water Breeder Reactor, which operated between 1977 and 1982 at the Shippingport Atomic Power Station, while employing a Thorium fuel ... -
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 ... -
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. ... -
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 ... -
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 ... -
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 ... -
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 ... -
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) ...