Contribution of each isotope in structral material on radiation damage in a hybrid reactor

Küçük Resim Yok

Tarih

2016

Dergi Başlığı

Dergi ISSN

Cilt Başlığı

Yayıncı

E D P Sciences

Erişim Hakkı

info:eu-repo/semantics/openAccess

Özet

In this study, the fluids were used in the liquid first-wall, blanket and shield zones of the designed hybrid reactor system. In this study, salt-heavy metal mixtures consisting of 93-85% Li20Sn80 + 5% SFG-PuO2 and 2-10% UO2, 93-85% Li20Sn80 + 5% SFG-PuO2 and 2-10% NpO2, and 93-85% Li20Sn80 + 5% SFG-PuO2 and 2-10% UCO were used as fluids. In this study, the effect on the radiation damage of spent fuel-grade (SFG)-PuO2, UO2, NpO2 and UCO contents was investigated in the structural material of a designed fusion-fission hybrid reactor system. In the designed hybrid reactor system were investigated the effect on the radiation damage of the selected fluid according to each isotopes of structural material in the structural material for 30 full power years (FPYs). Three-dimensional analyses were performed using the most recent MCNPX-2.7.0 Monte Carlo radiation transport code and the ENDF/B-VII.0 nuclear data library.

Açıklama

International Conference on Theoretical and Experimental Studies in Nuclear Applications and Technology (TESNAT) -- APR 28-30, 2016 -- Mustafa Kemal Univ, Hatay, TURKEY

Anahtar Kelimeler

3-Dimensional Neutronic Calculations, Structural Material, Apex Reactor

Kaynak

Theoretical and Experimental Studies in Nuclear Applications and Technology (Tesnat 2016)

WoS Q Değeri

N/A

Scopus Q Değeri

N/A

Cilt

128

Sayı

Künye