A review on the potential use of austenitic stainless steels in nuclear fusion reactors
Various engineering materials; austenitic stainless steels, ferritic/martensitic steels,
vanadium alloys, refractory metals and composites have been suggested as candidate …
vanadium alloys, refractory metals and composites have been suggested as candidate …
Neutronic analysis of a tokamak hybrid blanket cooled by thorium-molten salt fuel mixture
In this study, a novel approach has been investigated by using a mixture of thorium and
molten salts as a dual-purpose coolant and medium for the production of fissile fuel in a …
molten salts as a dual-purpose coolant and medium for the production of fissile fuel in a …
Neutronic study on the effect of first wall material thickness on tritium production and material damage in a fusion reactor
In this study, the effects of changing first wall materials and their thicknesses on a reactor
were investigated to determine the displacement per atom (DPA) and gas production …
were investigated to determine the displacement per atom (DPA) and gas production …
Monte Carlo calculation of radiation damage in first wall of an experimental hybrid reactor
HM Şahin - Annals of Nuclear Energy, 2007 - Elsevier
This work was focused on the neutronic calculation of the nuclear parameters (neutron
spectrum, displacement per atom (DPA), gas production, tritium breeding ratio (TBR) …
spectrum, displacement per atom (DPA), gas production, tritium breeding ratio (TBR) …
Modified APEX reactor as a fusion breeder
An advanced fusion reactor project, called APEX, with improved effectiveness has been
developed using a protective flowing liquid wall for tritium breeding and energy transfer. In …
developed using a protective flowing liquid wall for tritium breeding and energy transfer. In …
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) …
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 …
mixing the fertile fuel with natural-UO2 and LWR (light water reactors) spent nuclear fuel …
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 …
Monte Carlo calculation for various enrichment lithium coolant using different data libraries in a hybrid reactor
The main objective of this study is to compare the effect of the natural lithium and lithium with
different enrichments between 10% and 90% on neutronic parameters; such as tritium …
different enrichments between 10% and 90% on neutronic parameters; such as tritium …
Study on the fusion reactor performance with different materials and nuclear waste actinides
In this study, both pure fusion blanket and fusion‐fission (hybrid) reactor blanket
performance were investigated and discussed separately in two phases. In the first phase, a …
performance were investigated and discussed separately in two phases. In the first phase, a …