Results 21 to 30 of about 4,264 (289)
Conceptual design of solid-type Pb x Li y eutectic alloy breeding blanket for CFETR
Nuclear Fusion, 2023 As a key component of the Chinese Fusion Engineering and Test Reactor (CFETR), the blanket is responsible for tritium breeding, neutron shielding and energy conversion.
K. Jiang, Q. Wu, L. Chen, S. Liu
doaj +2 more sources
Design and Integration of the EU-DEMO Water-Cooled Lead Lithium Breeding Blanket
Energies, 2023 The water-cooled lead lithium breeding blanket (WCLL BB) is one of two BB candidate concepts to be chosen as the driver blanket of the EU-DEMO fusion reactor.
P Arena, G Bongiovi, Ilenia Catanzaro
exaly +3 more sources
The effect of Li2TiO3 pebbles on the mechanical properties of ARAA under breeding blanket conditions
Nuclear Materials and EnergyThe breeding blanket serves as a critical element for achieving a self-sustaining tritium cycle and generating sufficient energy in fusion reactors.
Yunsong Jung +4 more
doaj +2 more sources
Nuclear Engineering and TechnologyFusion reactors produce high-energy neutrons through the Deuterium-Tritium (DT) reaction. The long-term performance verification and structural integrity assessment of the breeding blanket under continuous plasma operation are essential for the ...
Hyoseong Gwon +3 more
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Impact of blanket material and configuration on the size of a tokamak fusion reactor
Nuclear Materials and Energy, 2021 On the basis of the Korean fusion roadmap, conceptual design of the DEMO and R&D on the breeding blanket are ongoing. This article addresses the impact of blanket material and configuration on the tritium breeding, shielding characteristics, and ...
Bong Guen Hong
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Neutronic analysis of effects of inboard materials on the size of a tokamak fusion reactor
Nuclear Materials and Energy, 2021 The effects of inboard materials on the size of a tokamak fusion reactor were studied based on reactor system parameters determined through a coupled analysis of tokamak systems and neutron transport. With an inboard blanket, the shielding capability was
B.G. Hong, W. Cho
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Neutronic Activity for Development of the Promising Alternative Water-Cooled DEMO Concepts
Applied Sciences, 2023 An emerging breeding blanket that fulfills performance criteria, meets the safety requirements, and is reliable enough to meet the plant availability is a challenging issue that assumes complex studies involving numerous neutronic analyses based on the ...
Pavel Pereslavtsev +3 more
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Materials for breeding blankets [PDF]
Journal of Nuclear Materials, 1996 There are several candidate concepts for tritium breeding blankets that make use of a number of special materials. These materials can be classified as Primary Blanket Materials, which have the greatest influence in determining the overall design and performance, and Secondary Blanket Materials, which have key functions in the operation of the blanket ...
Mattas, R. F., Billone, M. C.
openaire +1 more source
AIP Advances, 2023 The Chinese Fusion Engineering Test Reactor (CFETR) is a magnetic confinement fusion reactor independently designed and developed by China, which is based on the ITER design experience.
Jie Li +7 more
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Multiphysics Optimization for First Wall Design Enhancement in Water-Cooled Breeding Blankets
Nuclear Materials and Energy, 2021 The commercial feasibility of the first fusion power plant generation adopting D-T plasma is strongly dependent upon the self-sustainability in terms of tritium fuelling. Within such a kind of reactor, the component selected to house the tritium breeding
Ruggero Forte +3 more
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