Ara
Toplam kayıt 51, listelenen: 1-10
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, ...
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 ...
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 ...
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 ...
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. ...
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 ...
Cobra-Tf Yazılımı ile Soğutucu Kaybı Kazasında Akışın Yeniden Sağlanması Fazının Modellenmesi ve Model Belirsizliklerinin İncelenmesi
(Eğitim Bilimleri Enstitüsü, 2019)
Best estimate codes used in the safety analysis, licensing, research and development fields frequently are cost efficient, quick and reliable tools. For these codes which are widely used by the industry, universities 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 ...
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, ...