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Advanced Power Conversion Efficiency in Inventive Plasma for Hybrid Toroidal Reactor    
Yazarlar
Prof. Dr. Aybaba HANÇERLİOĞULLARI Prof. Dr. Aybaba HANÇERLİOĞULLARI
Kastamonu Üniversitesi, Türkiye
Mesut Cini
Kastamonu University, Turkey
Murat Güdal
Kastamonu University, Turkey
Özet
Apex hybrid reactor has a good potential to utilize uranium and thorium fuels in the future. This toroidal reactor is a type of system that facilitates the occurrence of the nuclear fusion and fission events together. The most important feature of hybrid reactor is that the first wall surrounding the plasma is liquid. The advantages of utilizing a liquid wall are high power density capacity good power transformation productivity, the magnitude of the reactor's operational duration, low failure percentage, short maintenance time and the inclusion of the system's simple technology and material. The analysis has been made using the MCNP Monte Carlo code and ENDF/B-V-VI nuclear data. Around the fusion chamber, molten salts Flibe (LI 2 BeF 4 ), lead-lithium (PbLi), Li-Sn, thin-lityum (Li 20 Sn 80 ) have used as cooling materials. APEX reactor has modeled in the torus form by adding nuclear materials of low significance in the specified percentages between 0 and 12 % to the molten salts. In this study, the neutronic performance of the APEX fusion reactor using various molten salts has been investigated. The nuclear parameters of Apex reactor has been searched for Flibe (LI 2 BeF 4 ) and Li-Sn, for blanket layers. In case of usage of the Flibe (LI 2 BeF 4 ), PbLi, and thin-lityum (Li 20 Sn 80 ) salt solutions at APEX toroidal reactors, fissile material production per source neutron, tritium production speed, total fission rate, energy reproduction factor has been calculated, the results obtained for both salt solutions are compared. © 2013 Springer Science+Business Media New York.
Anahtar Kelimeler
Apex | Blanket | Hybrid | Mcnp | Toroid
Makale Türü Özgün Makale
Makale Alt Türü SSCI, AHCI, SCI, SCI-Exp dergilerinde yayımlanan tam makale
Dergi Adı Journal of fusion Energy
Dergi ISSN 0164-0313
Dergi Tarandığı Indeksler SCI
Makale Dili İngilizce
Basım Tarihi 01-2013
Cilt No 32
Sayı 6
Sayfalar 607 / 614
Doi Numarası 10.1007/s10894-013-9621-1
BM Sürdürülebilir Kalkınma Amaçları
Atıf Sayıları
SCOPUS 2
Advanced Power Conversion Efficiency in Inventive Plasma for Hybrid Toroidal Reactor

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