Nükleer Enerji Mühendisliği Bölümü Tez Koleksiyonu
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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 ... -
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 ... -
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 ... -
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 ... -
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 ... -
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 ... -
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. ... -
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 ... -
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 ... -
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 ... -
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 ... -
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) ... -
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 ... -
Cobra-Tf Yazılımı ile Soğutucu Kaybı Kazasında Akışın Yeniden Sağlanması Fazının Modellenmesi ve Model Belirsizliklerinin İncelenmesi
(Eğitim Bilimleri Enstitüsü, 2019)Best estimate codes used in the safety analysis, licensing, research and development fields frequently are cost efficient, quick and reliable tools. For these codes which are widely used by the industry, universities and ... -
Kullanılmış Nükleer Yakıtın Yatay Jeolojik Bertarafının Isıl Analizleri
(Fen Bilimleri Enstitüsü, 2019)Geological disposal is the most accepted method for permanent disposal of spent nuclear fuel and high-level waste. There are various geological disposal concepts under development in many countries and these concepts have ... -
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 ... -
Düzleştirici Filtresiz Tedavi Sistemleri İçin Kalem Huzme Kerneli Geliştirilmesi
(Fen Bilimleri Enstitüsü, 2019-01-18)Pencil beam algorithm is a fast and accurate method for dose computation at Radiotherapy. This algorithm was developed for filtered x-ray energies. The aim of this study was developing pencil beam kernels by utilizing x-ray ... -
Nükleer Güç Santrallerinde Ağır Kazalar İçin 3+ Seviye Olasılıklı Güvenlik Analizi Yönteminin Geliştirilmesi Ve Akkuyu Nükleer Güç Santrali İçin Uygulanması
(Fen Bilimleri Enstitüsü, 2018)The purpose of this thesis is to develop 3+ level probabilistic safety analysis (PSA) method for severe accidents in nuclear power plants and to apply the developed method to Akkuyu Nuclear Power Plant. For this purpose, ...
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