Nükleer Enerji Mühendisliği Bölümü: Güncel gönderi
Toplam kayıt 47, listelenen: 41-47
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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 ...