Yayıncı "Fen Bilimleri Enstitüsü" Nükleer Enerji Mühendisliği Bölümü Tez Koleksiyonu için listeleme
Toplam kayıt 39, listelenen: 1-20
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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 ... -
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 ... -
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 ... -
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 ... -
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 ... -
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 ... -
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 ... -
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 ... -
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 ...
