Browsing Nükleer Enerji Mühendisliği Bölümü Tez Koleksiyonu by Type "info:eu-repo/semantics/masterThesis"
Now showing items 1-20 of 26
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1x3 Düzenindeki Ayıraçlı Bir Yakıt Demetinde Akışın Türbülans Karakteristiklerinin Hesaplamalı Akışkanlar Dinamiği Metoduyla İncelenmesi
(Fen Bilimleri Enstitüsü, 2018-06-27)In nuclear reactor analysis, understanding the effects of spacer grids on flow have an important place in determining the reactor thermal-hydraulic performance and ensuring that reactor works under reliable operating ... -
Basınçlı Su Reaktör Kabının Favor (Fracture Analysis Of Vessels Oak Ridge) Kodu ile Yapısal Analizinin Yapılması
(Fen Bilimleri Enstitüsü, 2018-11-13)Pressure vessels are the most important components of nuclear reactors in the view of protecting its integrity. In the past 30 years there have been a great development and innovative studies about the fracture mechanics ... -
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 ... -
Irıs Küçük Modüler Reaktörünün (Smr) Relap5/Scdapsım Sistem Kodu İle Modellenmesi
(Fen Bilimleri Enstitüsü, 2018)Due to many reasons such as its compact design, low initial investment costs, shorter installation times compared to conventional nuclear power plants, compatibility with nuclear disarmament treaty, compatibility of ... -
ISIL-NÖTRONİK ETKİLEŞİMLERİN URANYUM-TORYUM İÇEREN NÜKLEER YAKIT ELEMANLARININ TESİR KESİTLERİNE ETKİSİ
(Fen Bilimleri Enstitüsü, 2017-06)Neutron effective cross sections those define the interactions of neutrons with fuel elements are important parameters in defining operational and safety limitations of nuclear reactors. Hence, generation of these cross ... -
Isıl-Nötronik Etkileşimlerin Ve Nükleer Veri Kütüphanelerindeki Belirsizliklerin Nötronik Parametrelere Etkisi
(Fen Bilimleri Enstitüsü, 2017-06)Recently, investigation of effects of simplifications on nuclear models and used nuclear data libraries on calculation results have gained importance. Predicting uncertainties caused by these effects will provide more ... -
Isıl-Nötronik Etkileşimlerin Yakıt Elemanlarının Tesir Kesitlerine Etkisi
(Fen Bilimleri Enstitüsü, 2017)Accurate and precise neutronics calculations are important for reactor safety while defining safety limits for nuclear reactors. These calculations include the generation of neutron cross sections, as well. Some simplifications, ... -
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. ... -
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 ...