Nükleer Enerji Mühendisliği Bölümü: Güncel gönderi
Toplam kayıt 51, listelenen: 41-51
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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 ... -
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 ... -
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 ...