Browsing by Author "Bayrak, M"
Now showing items 1-4 of 4
-
Investigation of neutronic potential of a moderated (D-T) fusion driven hybrid reactor fueled with thorium to breed fissile fuel for LWRs
The potential of a moderated hybrid reactor fueled with ThC2 or ThF4 is investigated by a PF (plant factor) 75% under a first wall fusion neutron current load of 5 MW/m(2) LWR (Light Water Reactor) fuel rods containing ... -
Neutronic analysis of denaturing plutonium in a thorium fusion breeder and power flattening
The purpose of this study is to denature nuclear weapon grade quality plutonium in a thorium fusion breeder. Ten fuel rods containing the mixture of ThO2 and PuO2 are placed in a radial direction in the fissile zone where ... -
Power flattening and minor actinide burning in a thorium fusion breeder
A neutronic analysis has been performed for a thorium fusion breeder with a special task of burning minor actinides Np-237, Am-241, Am-243 and Cm-244 and production of U-233, Pu-238, Am-242m and Cm-245 for spacecraft ... -
Spent mixed oxide fuel rejuvenation in fusion breeders
A fusion breeder is presented for the rejuvenation of spent nuclear fuel. A (D, T) fusion reactor acts as an external high energetic (14.1 MeV) neutron source. The fissile fuel zone, containing ten rows in radial direction, ...
