Nükleer Enerji Mühendisliği Bölümü Tez Koleksiyonu: Güncel gönderi
Toplam kayıt 42, listelenen: 21-40
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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, ... -
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 ... -
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 ... -
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 ... -
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. ... -
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, ... -
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 ... -
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 ... -
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 ... -
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 ... -
VVER REAKTÖRÜNDE TORYUM-URANYUM YAKITLARIN ISIL-HİDROLİK PERFORMANS ANALİZİ
(Fen Bilimleri Enstitüsü, 2017-06-28)Today, current nuclear reactors’ future depends on uranium reserves. Researches for materials that can be replaced with uranium or can be used with uranium to obtain similar performances with uranium or better ... -
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 ... -
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 ... -
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 ... -
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, ... -
Design of Piercing Beam Port of Itu Triga Mark II Research Reactor for Bnct Application
(Fen Bilimleri Enstitüsü, 2015)Main aim of this study is to design the piercing beam port (PBP) of İstanbul Technical University TRIGA Mark II Research and Training Reactor (ITU-TRR) for the purpose of nuclear applications. The nuclear application ... -
Back-End Nuclear Fuel Cycle Options: Effects on High Level Waste Management and Disposal
(Fen Bilimleri Enstitüsü, 2013)In this thesis, back end fuel cycle options for Pressurized Water Reactor are discussed in terms of effects on high level waste management and, more specifically, on geological disposal. Once-through and alternative closed ... -
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 ... -
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 ...