Browsing Nükleer Enerji Mühendisliği Bölümü Tez Koleksiyonu by Title
Now showing items 16-35 of 38
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Kaynar Su Reaktörü Kullanılmış Yakıt Depolama Havuzunda Akış Kaybı Kazası Analizi
(Fen Bilimleri Enstitüsü, 2018-06)In March 2011, Japan was faced with the greatest natural disaster of its history. According to the Richter scale, the great earthquake magnitude of 8.9 was followed by a devastating tsunami, reaching 10-15 meters. After ... -
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 ... -
Kor İçi Yakıt Yönetim Kod Sistemi Geliştirilmesi
(Fen Bilimleri Enstitüsü, 2014)This study consists of six different computer programs. These programs are based on one dimensional core loading pattern and fuel loading pattern of Almaraz II Nuclear Power Plant for easy understanding of core loading ... -
Kullanılmış Nükleer Yakıt Depolama Kabının Isıl Analizi
(Fen Bilimleri Enstitüsü, 2015)In this study, thermal analysis was performed for the TN-24P cask by using Computational Fluid Dynamics method. For the analysis, ANSYS Fluent as a CFD tool was selected since it has the proper finite volume methods to ... -
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 ... -
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. ... -
Küçük Modüler Nükleer Reaktörün 3-Boyutlu Tasarımı ve Toryum Kullanımı ile Analizi
(Fen Bilimleri Enstitüsü, 2017)The aim of this study is to investigate the thorium utilization for a novel Small Modular Nuclear Reactor designed with this study by generating the 3-dimensional (3D) model of the reactor. For this, MCNP6.1.1b code is ... -
Modeling and Simulation of X-Rays Radiotherapy
(Fen Bilimleri Enstitüsü, 2012)In this thesis, various concepts for Microbeam Radiation Therapy (MRT) technique were simulated and dosimetric calculations were performed with the Monte Carlo technique. In the first part, the dosimetric Monte Carlo ... -
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, ... -
Nükleer Maddelerin İzotopik İçeriğinin Monte Carlo Yöntemi ile Belirlenmesi
(Fen Bilimleri Enstitüsü, 2018-11-09)Uranium needs to be enriched in order to be used in Light Water Reactors (LWR) as fuel cells. This process can be accomplished in enrichment facilities by increasing U-235 isotope mass content in the uranium element. ... -
Nükleer Santrallerde Yangından Korunmanın Önemi ve Compbrn III Kodu Kullanılarak Tipik Bir Dizel Jenaratör Odasında Yangının Modellenmesi
(Fen Bilimleri Enstitüsü, 2013)This study emphasizes Nuclear Power Plant (NPP) fire safety, and discusses primary elements vulnerable to fire and fire accidents in NPP operation history including their causes. Fire Hazard Analysis, which has to be ... -
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 ... -
Psb-Vver Test Tesisi Deneylerinin Termal Hidrolik Olarak Modellenmesiyle Relap5 Kodunun Doğrulanması
(Fen Bilimleri Enstitüsü, 2018)In this work loss of coolant accident analysis was done by simulating an experiment which assumes a small break in cold leg between main circulation pump and pressure vessel. Behaviour of pressure, temperature, power, break ... -
PWR-CANDU6 BİRLEŞİK YAKIT ÇEVRİMİ VE CANDU6’DA URANYUM + TORYUM KULLANIMI
(Fen Bilimleri Enstitüsü, 2017-06)In this study, burnup analyses were made for PWR-CANDU6 combined fuel cycles in which PWR spent fuel is used as fuel in CANDU6. Besides, for the once-through fuel cycle, use of uranium + thorium (U+Th) in CANDU6 were looked ... -
RELAP/SCDAPSIM/MOD3.4 KODU KULLANILARAK ULUSLARARASI STANDARTLAŞTIRMA PROBLEMİ ISP NO.31'İN ANALİZİ
(Fen Bilimleri Enstitüsü, 2018)Under the scope of international "Sever Fuel Damage (SFD)" program, Cora experiments are actualized to study the events of the severe accidents. Cora-13 out of pile experiment enlightened us about fuel failure mechanism, ... -
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 ... -
Stokastik Programlama Yaklaşımı ile Elektrik Üretim Endüstrisinin Modellenmesi
(Fen Bilimleri Enstitüsü, 2018)This thesis focuses on the development of a framework and mathematical models to formulate generation expansion planning (GEP) models that include multiple objectives; by means of appropriately considering conventional and ... -
Süper Kritik Su Reaktörlerinde Alumina Oluşturan Östenitik Çelik Yakıt Zarf Malzemesinin Radyasyon Hasar Parametrelerinin Belirlenmesi
(Fen Bilimleri Enstitüsü, 2013)This thesis discusses the subject of Alumina Forming Austenitic Stainless Steels (AFA) which can be a candidate material for the Super Critical Water Reactors (SCWRs) fuel claddings. The literature survey shows ...