Results 11 to 20 of about 502,482 (107)

The Design of Water Loop Facility for Supporting the WCLL Breeding Blanket Technology and Safety [PDF]

open access: goldEnergies, 2023
The WCLL Breeding Blanket of DEMO and the Test Blanket Module (TBM) of ITER require accurate R&D activities, i.e., concept validation at a relevant scale and safety demonstrations. In view of this, the strategic objective of the Water Loop (WL) facility,
Alessandra Vannoni   +16 more
doaj   +13 more sources

Magneto-Convective Analyses of the PbLi Flow for the EU-WCLL Fusion Breeding Blanket [PDF]

open access: goldEnergies, 2021
The Water Cooled Lithium Lead (WCLL) breeding blanket is one of the driver blanket concepts under development for the European Demonstration Reactor (DEMO). The majority of the blanket volume is occupied by flowing PbLi at eutectic composition.
F.R. Urgorri   +2 more
doaj   +6 more sources

Investigation of the DEMO WCLL Breeding Blanket Cooling Water Activation [PDF]

open access: greenFusion Engineering and Design, 2020
Abstract Within the framework of the activities foreseen by the EUROfusion action on the cooling water activation assessment for a DEMO reactor equipped with a Water Cooled Lithium Lead Breeding Blanket (WCLL BB), the University of Palermo is involved in the assessment of dose rates induced by the decay of nitrogen radioisotopes produced by water ...
Gandolfo Alessandro Spagnuolo   +2 more
exaly   +10 more sources

Magnetohydrodynamic simulation of the WCLL breeding blanket with helical cooling pipes

open access: hybridFusion Engineering and Design
The Water-Cooled Lead Lithium (WCLL) is a Breeding Blanket (BB) concept presently in the development phase for implementation in the DEMO fusion reactor demonstrator. The Lead lithium eutectic alloy (PbLi) breeder is moved at a slow velocity to diminish Magnetohydrodynamics (MHD) pressure losses.
Simone Siriano, Alessandro Tassone
exaly   +5 more sources

Thermo-hydraulic analysis of EU DEMO WCLL breeding blanket [PDF]

open access: greenFusion Engineering and Design, 2018
Abstract In the frame of EUROfusion Work Package Breeding Blanket, thermal-hydraulic engineering analyses were carried out at ENEA Brasimone, in close cooperation with Sapienza University of Rome, to investigate thermal and fluid-dynamic behavior of the Water Cooled Lithium Lead Breeding Blanket, which is a candidate option for the European DEMO ...
Gianfranco Caruso   +2 more
exaly   +6 more sources

Dynamic thermal-hydraulic modelling of the EU DEMO WCLL breeding blanket cooling loops [PDF]

open access: hybridFusion Engineering and Design, 2017
A global thermal-hydraulic model of the EU DEMO tokamak, based on an object-oriented approach using the Modelica language, is currently under development at Politecnico di Torino. The first module of the global model will simulate the dynamics of the blanket cooling system and it will be able to investigate different coolant options and different ...
Laura Savoldi   +2 more
exaly   +7 more sources

Helical-shaped double wall tubes solution for the breeding zone cooling in the WCLL breeding blanket

open access: hybridFusion Engineering and Design
One of the two most promising Breeding Blanket (BB) concepts to be chosen as driver design of the EU-DEMO fusion reactor is the Water-Cooled Lead Lithium (WCLL) BB. A crucial point of this key component is the cooling of the BB structural elements and of the Lithium-Lead alloy, used as neutronic multiplier and Tritium breeder.
Fabio Moro   +2 more
exaly   +4 more sources

Activities in Divertor Reflector and Linear Plates Using WCLL and HCPB Breeding Blanket Concepts [PDF]

open access: goldEnergies, 2021
In fusion devices, such as European Demonstration Fusion Power Reactor (EU DEMO), primary neutrons can cause material activation due to the interaction between the source particles and the targeting material.
Simona Breidokaité   +1 more
doaj   +5 more sources

3D Transient CFD Simulation of an In-Vessel Loss-of-Coolant Accident in the EU DEMO WCLL Breeding Blanket [PDF]

open access: goldEnergies, 2023
The in-vessel Loss-of-Coolant Accident (LOCA) is one of the design basis accidents in the design of the EU DEMO tokamak fusion reactor. System-level codes are typically employed to analyse the evolution of these transients.
Mauro Sprò   +2 more
doaj   +4 more sources

On the impact of the heat transfer modelling approach on the prediction of EU-DEMO WCLL breeding blanket thermal performances [PDF]

open access: greenFusion Engineering and Design, 2020
The Water-Cooled Lithium-Lead Breeding Blanket is a key component of a fusion power plant, in charge of ensure Tritium production, shield Vacuum Vessel and magnets and remove the heat power deposited by radiation and particles arising from plasma.
Gianfranco Caruso   +2 more
exaly   +7 more sources

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