Ara
Toplam kayıt 38, listelenen: 11-20
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 ...
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 ...
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 ...
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 ...
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 ...
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 ...
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 ...