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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   +3 more
openaire   +4 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   +2 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).
Jiang, Kecheng   +4 more
openaire   +1 more source

Pre-analysis of the WCLL breeding blanket mock-up neutronics experiment at the frascati neutron generator

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 ...
Flammini, D.   +7 more
openaire   +1 more source

Multiphysics tritium transport modelling in WCLL breeding blankets: Influence of MHD effects and neutron damage

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
openaire   +1 more source

Numerical Study of Mhd Mixed Convection Flow in The  EU Demo Wcll Breeding Blanket

Fusion Engineering and Design, 2023
Long Chen, Xuan Zheng, Mingjiu Ni
openaire   +1 more source

Neutron Flux in EU DEMO Divertor Cassette Body Using HCPB and WCLL Breeding Blanket Models

Journal of Fusion Energy, 2022
Simona Breidokaite, Gediminas Stankunas
openaire   +1 more source

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   +1 more source

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