Power flattening in a catalyzed deuterium-deuterium fusion-driven hybrid blanket using nuclear waste actinides
S Şahin - Nuclear Technology, 1990 - Taylor & Francis
A straightforward numerical-graphical method is applied to achieve a flat fission power
density (FPD) in a catalyzed deuterium-deuterium fusion-driven hybrid blanket by using a …
density (FPD) in a catalyzed deuterium-deuterium fusion-driven hybrid blanket by using a …
Rejuvenation of light water reactor spent fuel in fusion blankets
The possibility of spent nuclear fuel rejuvenation in fusion reactors is investigated for both
(D, T) and catalysed (D, D) modes. The analysis is conducted for light water reactor (LWR) …
(D, T) and catalysed (D, D) modes. The analysis is conducted for light water reactor (LWR) …
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 …
reactor acts as an external high energetic (14.1 MeV) neutron source. The fissile fuel zone …
Rejuvenation of the LWR spent fuel in (D–T) driven hybrid reactors
S Ünalan - Fusion Engineering and Design, 1998 - Elsevier
The possibility of LWR spent fuel rejuvenation in (D, T)(Deuterium and Tritium) driven hybrid
reactors having 12.5 cm of the fissile zone thickness is investigated for various plasma …
reactors having 12.5 cm of the fissile zone thickness is investigated for various plasma …
Analysis of the rejuvenation performance of hybrid blankets by using uranium fuels (UN, UC, UO2, U3Si2) and different coolants for various volume fraction
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 …
and coolants. Neutronic performances of the deuterium–tritium (D–T) driven hybrid blankets …
Temperature distribution in nuclear fuel rod and variation of the neutronic performance parameters in (D–T) driven hybrid reactor system
Temperature distribution in nuclear fuel rod and variation of the neutronic performance
parameters are investigated for different coolants under various first wall loads (Pw= 2, 5, 7 …
parameters are investigated for different coolants under various first wall loads (Pw= 2, 5, 7 …
Light and heavy water cooled hybrid reactors for rejuvenation of LWR spent fuels
This study analyzes the rejuvenation performance and energy production of D–T driven
hybrid blankets fueled by LWR spent fuel and cooled by heavy water (D2O) and light water …
hybrid blankets fueled by LWR spent fuel and cooled by heavy water (D2O) and light water …
Neutronic analysis of denaturing plutonium in a thorium fusion breeder and power flattening
H Yapıcı, M Bayrak - Energy conversion and management, 2005 - Elsevier
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 …
thorium fusion breeder. Ten fuel rods containing the mixture of ThO2 and PuO2 are placed …
Rejuvenation of the CANDU Spent Fuel in (DT)–Driven Hybrid Reactors
S ÜNalan - Fusion technology, 1998 - Taylor & Francis
The possibility of Canada deuterium uranium reactor (CANDU) spent-fuel rejuvenation in
deuterium-tritium (DT)-driven hybrid reactors having 17.8 cm of fissile zone thickness is …
deuterium-tritium (DT)-driven hybrid reactors having 17.8 cm of fissile zone thickness is …
Analysis of temperature distribution, burn‐up and breeding parameters in nuclear fuel rod in fusion–fission reactor system fueled with mixed ThO2‐UO2 fuel
O İpek - International Journal of Energy Research, 2011 - Wiley Online Library
Temperature distribution in nuclear fuel rod, burn‐up (BU), possibility of nuclear fuel
rejuvenation and breeding parameters are investigated for different coolants under various …
rejuvenation and breeding parameters are investigated for different coolants under various …