Results 81 to 90 of about 410 (102)
Investigation of the DEMO WCLL Breeding Blanket Cooling Water Activation
, 2019 Chiovaro, P. +8 more
openaire +3 more sources
Conference paper presented at PHYSOR 2026 - The International Conference on Physics of Reactors. Published in Proceedings of PHYSOR 2026 International Conference. ISBN: 979-12-81583-46-7. Conference website: https://www.physor2026.org/. Session: S02. Neutronics for Fusion. Paper ID: 658. Copyright transferred to Politecnico di Torino by the authors for
L. Piccinini +4 more
openaire +1 more source
Study of a WCLL breeding blanket concept for a compact nuclear fusion reactor
International audienceDesign and optimization of a breeding blanket for a fusion reactor.
David-Menendez, Raphael +1 more
core
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
Fusion Engineering and Design, 2020 Abstract The Water Cooled Lithium Lead (WCLL) is one of the breeding blanket (BB) concept candidate for the future European Demonstration Fusion Power Reactor (DEMO). In the frame of the EUROfusion Consortium, a WCLL BB mock-up neutronics experiment will be performed at the 14 MeV Frascati Neutron Generator (FNG) irradiation facility, devoted to the ...
D Flammini +2 more
exaly +3 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).
Kecheng Jiang +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)
Candido, Luigi +6 more
openaire +3 more sources
MHD and heat transfer analyses in PbLi radial channels for the EUROfusion WCLL breeding blanket
, 2019 The Water Cooled Lithium Lead (WCLL) breeding blanket concept is the one of the PbLi-based concepts under development within the framework of the EUROfusion project. This concept is characterized by cooling the PbLi using water tubes embedded in the PbLi flow.
Fernando Roca Urgorri +7 more
openaire +2 more sources
Tritium transport model at breeder unit level for HCLL breeding blanket [PDF]
Fusion Engineering and Design, 2019 Abstract The Helium-Cooled Lithium Lead (HCLL) breeding blanket is one of the European blanket designs proposed for DEMO reactor. A tritium transport model is fundamental for the correct assessment of both design and safety, in order to guarantee tritium self-sufficiency and to characterize tritium concentrations, inventories and losses.
Raffaella Testoni +3 more
openaire +2 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.
Dark, James +3 more
core +3 more sources