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1. 
Cover image for Finite element modeling of pellet-clad mechanical interaction = Yakıt ile zarfın mekanik etkileşiminin sonlu elemanlar yöntemi ile modellenmesi
Finite element modeling of pellet-clad mechanical interaction = Yakıt ile zarfın mekanik etkileşiminin sonlu elemanlar yöntemi ile modellenmesi
Author 
Alim, Fatih. Nuclear Engineering Department According to the Regulations Thesis.
Preferred Shelf Number 
TEZ 4724 .A45 2000
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2. 
Cover image for Deterministic and probabilitic analysis of pressure vessel under PTS = Basınçlı termal şok altındaki basınç kabının deterministik ve probabilistik analizi
Deterministic and probabilitic analysis of pressure vessel under PTS = Basınçlı termal şok altındaki basınç kabının deterministik ve probabilistik analizi
Author 
Özdere, Oya. Nuclear Engineering Department According to the Regulations Thesis.
Preferred Shelf Number 
TEZ 4723 .O93 2000
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3. 
Cover image for Neutronic and thermal hydraulic analysis of dry cask storage systems = Kuru depolama sistemlerinin nötronik ve termal hidrolik analizi
Neutronic and thermal hydraulic analysis of dry cask storage systems = Kuru depolama sistemlerinin nötronik ve termal hidrolik analizi
Author 
Yavuz, Ufuk. Prepared in the Nuclear Engineering Department According to the Regulations Thesis.
Preferred Shelf Number 
TEZ 4922 .Y28 2000
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4. 
Cover image for Cost analysis and economic comparison for alternative fuel cycles in the heavy water cooled Canadian reactor (CANDU) = Ağır su soğutmalı KANADA (CANDU) reaktöründe alternatif yakıt çevrimleri için maliyet analizi ve ekonomik karşılaştırma
Cost analysis and economic comparison for alternative fuel cycles in the heavy water cooled Canadian reactor (CANDU) = Ağır su soğutmalı KANADA (CANDU) reaktöründe alternatif yakıt çevrimleri için maliyet analizi ve ekonomik karşılaştırma
Author 
Yılmaz, Serkan. Prepared in the Nuclear Engineering Department According to the Regulations Thesis.
Preferred Shelf Number 
TEZ 4919 .Y56 2000
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5. 
Cover image for Transient analysis of AP600 reactor by using RELAP5 system code = AP600 reaktörünün RELAP5 sistem kodu ile geçiş durumları analizi
Transient analysis of AP600 reactor by using RELAP5 system code = AP600 reaktörünün RELAP5 sistem kodu ile geçiş durumları analizi
Author 
Pezek, Enis. The Nuclear Engineering Department According To The Regulations Thesis
Preferred Shelf Number 
TEZ 4203 .P49 1999
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6. 
Cover image for Performance evaluation of parallel Monte Carlo method with variance reduction techniques = Varyans azaltma teknikleri ile paralel monte carlo metodunda performans analizi
Performance evaluation of parallel Monte Carlo method with variance reduction techniques = Varyans azaltma teknikleri ile paralel monte carlo metodunda performans analizi
Author 
Burak Bekar, Kürşat. The Nuclear Engineering Department According To Regulations Thesis.
Preferred Shelf Number 
TEZ 4899 .
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