Search Results for Nuclear Engineering Department Thesis.

1.

Cover image for A Comprehensive Experimental and Computational Analysis of Pressure Drop in Pipes and Fittings = Boru ve Bağlantılarda Çok Amaçlı Deneysel ve Hesaplamalı Basınç Düşümü Analizi

A Comprehensive Experimental and Computational Analysis of Pressure Drop in Pipes and Fittings = Boru ve Bağlantılarda Çok Amaçlı Deneysel ve Hesaplamalı Basınç Düşümü Analizi

Author

Duman, Veda. Nuclear Engineering Department Thesis.

Preferred Shelf Number

TEZ 9716 .D86 2010

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2.

Nuclear fuel management optimization using genetic algorithm = Genetik algoritma ile nükleer yakıt yönetimi optimizayonu

Author

Yılmazbayhan, Aylin. The Nuclear Engineering Department Thesis.

Preferred Shelf Number

TEZ 4426 .Y55 1999

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3.

Cover image for Effects of advanced fuel management strategies on fuel burnup = İleri nükleer yakıt yönetimi stratejilerinin yakıt kullanımına etkisi

Effects of advanced fuel management strategies on fuel burnup = İleri nükleer yakıt yönetimi stratejilerinin yakıt kullanımına etkisi

Author

Sarıkaya, Barış. The Nuclear Engineering Department Thesis.

Preferred Shelf Number

TEZ 4428 .S27 1999

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4.

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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5.

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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6.

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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7.

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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8.

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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9.

Candu-6 accident analysis : large breaks = Candu-6 reaktöründe kaza analizi : büyük kırıklar

Author

Kayrancı, Serkan. The Nuclear Engineering Department According to The Regultions Thesis.

Preferred Shelf Number

TEZ 4204 .K39 1999

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10.

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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