Results 91 to 100 of about 502,482 (107)
A novel approach to the study of magnetohydrodynamic effect on tritium transport in WCLL breeding blanket of DEMO [PDF]
Fusion Engineering and Design, 2021 Abstract The Water-Cooled Lithium Lead (WCLL) breeding blanket is one of the European blanket designs proposed for DEMO reactor. Tritium can permeate into the different structural materials, arising potential issues concerning the fuel self-sufficiency and can be lost into the environment with consequent radiological hazard for the population. Within
Luigi Candido, Fabio Moro, Marco Utili
exaly +4 more sources
Rationale and method for design of DEMO WCLL breeding blanket poloidal segmentation
Fusion Engineering and Design, 2017 Abstract One of the most critical components in the design of DEMO Power Plant is the Breeding Blanket. Currently, four candidates are investigated as options for DEMO. One of these is the Water Coolant Lithium Lead Breeding Blanket. A new concept design has been proposed and investigated in 2015.
Rocco Mozzillo +2 more
exaly +7 more sources
Investigation on cooling performance of WCLL breeding blanket first wall for EU DEMO
Fusion Engineering and Design, 2019 Abstract The Breeding Blanket (BB) First Wall (FW) is the first boundary separating the fusion plasma and its energetic particles from the rest of a Tokamak. The heat load specifications at different poloidal positions are reviewed according to the maximum heat load (surface radiation and charged particles).
Songlin liu +2 more
exaly +3 more sources
Tritium Transport in WCLL Outboard Breeding Blanket of EU-DEMO Reactor Under Pulsed Plasma Operation
Fusion Science and Technology, 2023 The accurate prediction of the tritium inventory and permeation fluxes in the water-cooled lithium-lead (WCLL) breeding blanket of the European DEMO fusion reactor is a key aspect for future thermonuclear power plant licensing. In this context, a tritium transport analysis is essential for the evaluation of the tritium retention in LiPb (15.7 at. % Li)
Luigi Candido +6 more
core +4 more sources
, 2023 The replenishment of tritium fuel in a breeding blanket is fundamental for the operation of commercial DT fusion reactors. Accurate modelling of hydrogen transport and inventories within the breeding blanket will be essential for safety issues and economic sustainability.
James Dark +3 more
core +5 more sources
Advancements in DEMO WCLL breeding blanket design and integration
International Journal of Energy Research, 2018 Gianfranco Caruso +2 more
exaly +2 more sources
Multiphysics tritium transport simulations of the WCLL breeding blanket for DEMO
Simulations multiphysiques du transport du tritium dans la couverture tritigène la WCLL pour OEMO Cette étude présente le développement d'un modèle multiphysique dont l'objectif et la simulation du transport du tritium dans la couverture tritigène de DEMO WCLL (Water Cooled Lithium Lead).
James Dark
openalex +3 more sources
Neutron Flux in EU DEMO Divertor Cassette Body Using HCPB and WCLL Breeding Blanket Models
Journal of Fusion Energy, 2022 Simona Breidokaité +1 more
openalex +2 more sources
Modelling of tritium transport in WCLL breeding blankets: influence of neutron induced damage
, 2022 James Dark +5 more
openalex +2 more sources
In the framework of the advanced design of the European DEMO nuclear fusion reactor, the Water-Cooled Lithium Lead (WCLL) concept represents one of the most promising options for the Breeding Blanket (BB) technology. Based on this assessment, the WCLL BB
MARCO COSCI
openalex +1 more source