Author/Authors
TAŞKOLU, Hakan Gazi Universitesi - Fen Bilimleri Enstitüsü, TURKEY , ACIR, Adem Gazi Universitesi - Teknoloji Fakültesi, TURKEY
Title Of Article
Neutronic Analysis of TRISO Coated Candu Spent Fuel in A Hybrid Reactor
شماره ركورد
15782
Abstract
In this study, time dependent performance of incineration of the TRISO fuel containing CANDU spent fuels in the Deuterium-Tritium (D-T) fusion driven hybrid reactor was investigated. Neutron transport calculations were performed by using XSDRNPM/SCALE 5 codes. In the reactor model, neutral lithium, flibe, flinabe and Li20Sn80 were used as coolants. In the calculations, the effect of TRISO fuel containing CANDU spent fuels on tritium breeding ratio (TBR), energy multiplication (M), fissile fuel breeding (FFB) and average burn up values were comparatively investigated. According to the time dependent calculations, it was observed that TRISO fuel containing CANDU spent fuels extends the burn-up.
From Page
129
NaturalLanguageKeyword
Fusion , Fission , TRISO fuel , CANDU spent fuel
JournalTitle
Journal Of Polytechnic
To Page
133
JournalTitle
Journal Of Polytechnic
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