Başlık için Nükleer Enerji Mühendisliği Bölümü Tez Koleksiyonu listeleme
Toplam kayıt 38, listelenen: 30-38
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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 ... -
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 ... -
RELAP/SCDAPSIM/MOD3.4 KODU KULLANILARAK ULUSLARARASI STANDARTLAŞTIRMA PROBLEMİ ISP NO.31'İN ANALİZİ
(Fen Bilimleri Enstitüsü, 2018)Under the scope of international "Sever Fuel Damage (SFD)" program, Cora experiments are actualized to study the events of the severe accidents. Cora-13 out of pile experiment enlightened us about fuel failure mechanism, ... -
Sonlu Hacimler Yöntemi ile Kor Nötronik Analizi
(Fen Bilimleri Enstitüsü, 2021-12-27)In this thesis, a code that can be used to perform 3 dimensional neutronics analysis of nuclear reactor cores is developed. The code discretizes two group neutron diffusion equations using finite volume method for the ... -
Stokastik Programlama Yaklaşımı ile Elektrik Üretim Endüstrisinin Modellenmesi
(Fen Bilimleri Enstitüsü, 2018)This thesis focuses on the development of a framework and mathematical models to formulate generation expansion planning (GEP) models that include multiple objectives; by means of appropriately considering conventional and ... -
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 ... -
Treat Reaktöründe Işınlanan Gelişmiş Metalik Alaşımların Radyasyon Hasarı Hesaplamaları
(Fen Bilimleri Enstitüsü, 2020)The new generation reactor concepts that have been designed so far are foreseen for a common goal for safer, longer-lasting, nuclear non-proliferation and more economical use of nuclear energy. The most important issue to ... -
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 ... -
VVER-1200 Reaktöründe Soğutucu Kaybı Kazası ve Belirsizlik Analizi
(Fen Bilimleri Enstitüsü, 2020)The objective of this thesis is to perform the thermal-hydraulic analysis of VVER-1200 reactor under Loss of Coolant Accident (LOCA) conditions including uncertainty calculations for the Peak Cladding Temperature (PCT) ...