Neutronic analysis of TRISO coated CANDU spent fuel in a fusion-fission hybrid reactor
2010
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Advisor: Doç. Dr. Adem Acır
Abstract (EN)
In this study present the effect of neutronic performance on the incineration of the TRISO fuel containing CANDU spent fuels in the Deuterium?Tritium (D-T) fusion driven hybrid reactor investigated as time dependent. Neutron transport calculations are performed by using XSDRNPM/SCALE 5 codes. Natural lithium, Flibe, Flinabe and Li20Sn80 is used as coolants. The impact of TRISO fuel containing CANDU spent fuels on tritium breeding (TBR), energy multiplication (M), total fission rate ( ? f), cumulative fissile fuel enrichment (CFFE), fissile fuel breeding (FFB), average burn up values are comparatively investigated. It is observed that the neutronic results affect from TRISO fuel containing CANDU spent fuels as regards extended burn up as time dependent.Key words: Fusion, Fission, TRISO fuel, CANDU spent fuel.
Author
Hakan Taşkolu
How to Cite
Hakan Taşkolu (Master Thesis). Neutronic analysis of TRISO coated CANDU spent fuel in a fusion-fission hybrid reactor, 2010, Gazi University.
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