Results 11 to 20 of about 2,424 (258)
Manufacturing Technology of Ceramic Pebbles for Breeding Blanket [PDF]
Materials, 2018 An open issue for the fusion power reactor is the choice of breeding blanket material. The possible use of Helium-Cooled Pebble Breeder ceramic material in the form of pebble beds is of great interest worldwide as demonstrated by the numerous studies and research on this subject.
R Lo Frano, Mónica Puccini
exaly +6 more sources
Structural assessment of the gripper interlock of the DEMO breeding blanket transporter. [PDF]
Heliyon, 2023 The maintenance of the DEMO Breeding Blanket (BB) remotely is a crucial aspect in development of the DEMO power plant. It is a challenge due to the huge mass of the BB segment of about 180 tons. A new concept for the BB transporter has recently been developed.
Mozzillo R +4 more
europepmc +6 more sources
Energies, 2023 Significant design efforts were undertaken during the Pre-Concept Design (PCD) phase of the European DEMO program to optimize the helium cooled pebble bed (HCPB) breeding blanket.
Guangming Zhou +2 more
exaly +3 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.
Rocco Mozzillo +2 more
exaly +3 more sources
Progress in EU Breeding Blanket design and integration
Fusion Engineering and Design, 2018 In Europe (EU), in the frame of the EUROfusion consortium activities, four Breeding Blanket (BB) concepts are being developed with the aim of fulfilling the performances required by a near-term fusion power demonstration plant (DEMO) in terms of tritium self-sufficiency and electricity production.
Rocco Mozzillo +2 more
exaly +7 more sources
Accident-tolerant hybrid ceramics for fusion breeding blanket
Materials & DesignIn a water-cooled ceramic breeding blanket for fusion reactors, hydrogen gas generation by steam oxidation of metallic Be compounds (i.e. neutron multiplier) in a loss-of-coolant accident (LOCA) raises major safety concerns.
Keisuke Mukai +3 more
doaj +2 more sources
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
doaj +1 more source
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
doaj +1 more source
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
doaj +1 more source
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