Browsing by Author "Yapici, H"
Now showing items 1-8 of 8
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Analysis of the rejuvenation performance of hybrid blankets by using uranium fuels (UN, UC, UO2, U3Si2) and different coolants for various volume fraction
Yapici, H; Ipek, O; Ozceyhan, V; Erisen, A (PERGAMON-ELSEVIER SCIENCE LTD, 2000)The possibility of nuclear fuel rejuvenation in fusion reactors is investigated for different fuels and coolants. Neutronic performances of the deuterium-tritium (D-T) driven hybrid blankets, fuelled with UN, UC, UO2 and ... -
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 ... -
Neutronic performance of proliferation hardened thorium fusion breeders
Production of denaturated fissile fuel in a thorium fusion breeder has been investigated by mixing the fertile fuel with natural-UO2 and LWR (light water reactors) spent nuclear fuel. Four different coolants (pressurised ... -
Numerical neutronic analysis of a natural lithium cooled fusion breeder fueled with UO2
Yapici, H; Ozceyhan, V (KING FAHD UNIV PETROLEUM MINERALS, 2000)The fissile breeding capability of a catalyzed-(D,D) and (D,T) fusion-fission (hybrid) reactor, fueled with spent UO2, is analyzed under first wall fusion neutron load of 5 MW/m(2) to provide nuclear fuel for LWRs. This ... -
Potential of a fusion-fission hybrid reactor using uranium for various coolants to breed fissile fuel for LWRs
Yapici, H; Curuttu, I; Ozceyhan, V; Kirbiyik, M (PERGAMON-ELSEVIER SCIENCE LTD, 1999)In this study, neutronic performances of the (D,T) driven hybrid blankets, fuelled with UC2 and UF4, are investigated under first wall load of 5 MW/m(2). The fissile fuel zone is considered to be cooled with three coolants: ... -
Proliferation hardening and power flattening of a thorium fusion breeder with triple mixed oxide fuel
Sahin, S; Ozceyhan, V; Yapici, H (PERGAMON-ELSEVIER SCIENCE LTD, 2001)The proliferation hardening of the U-233 fuel in a thorium fusion breeder has been realised successfully with a homogenous mixture of ThO2, natural-UO2 and CANDU spent nuclear fuel in the form of a triple mixed oxide (TMOX) ... -
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, ...
