Results 61 to 70 of about 119 (89)

WCLL breeding blanket design and integration for DEMO 2015: status and perspectives

Fusion Engineering and Design, 2017
Abstract Water-cooled lithium-lead breeding blanket is considered a candidate option for European DEMO nuclear fusion reactor. ENEA and the linked third parties have proposed and are developing a multi-module blanket segment concept based on DEMO 2015 specifications. The layout of the module is based on horizontal (i.e. radial-toroidal) water-cooling
Caruso G, Giovanni Mariano, Rocco Mozzillo   +2 more
exaly   +6 more sources

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Influence of hydrogen trapping on WCLL breeding blanket performances

Nuclear Fusion, 2021
Tritium transport simulations in Water-Cooled Lithium Lead (WCLL) breeding blankets have been performed with FESTIM. Fluid dynamics and heat transfer were coupled to evaluate how temperature and LiPb velocity fields affect Tritium transport. The 2D WCLL model consisted of tungsten, EUROFER and liquid LiPb. Tritium inventories and permeation fluxes have
Dark, James, Delaporte-Mathurin, Rémi, Charles, Yann, Hodille, Etienne, Grisolia, Christian, Mougenot, Jonathan   +5 more
openaire   +3 more sources

Thermo-hydraulic analysis of EU DEMO WCLL breeding blanket

Fusion 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 ...
Caruso G, Alessandro Del Nevo, Emanuela Martelli   +2 more
exaly   +2 more sources

Analysis of EM loads on DEMO WCLL breeding blanket during VDE-up

Fusion Engineering and Design, 2018
Abstract This work presents the development of a DEMO EM model based on the WCLL design able to evaluate EM loads during normal and off-normal operations. The model has the capability to use periodic boundary conditions (in order to analyze EM transients in presence of both toroidal and poloidal field) and elements supporting non-linear magnetic ...
Alessandro Del Nevo, Ivan Alessio Maione, Fabio Villone   +2 more
exaly   +6 more sources

A novel approach to the study of magnetohydrodynamic effect on tritium transport in WCLL breeding blanket of DEMO

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   +2 more
exaly   +2 more sources

Magneto-convective effect on tritium transport at breeder unit level for the WCLL breeding blanket of DEMO

Fusion Engineering and Design, 2020
Abstract The Water-Cooled Lithium-Lead (WCLL) is one of the four breeding blanket concepts proposed by Europe in view of its DEMO reactor. The velocity field of the electrically conducting lead-lithium eutectic alloy inside the blanket is strongly influenced by the external magnetic field used for plasma confinement combined with buoyancy effect. The
Luigi Candido, Marco Utili, Ciro Alberghi   +2 more
exaly   +3 more sources

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

Fusion 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, Alessandro Del Nevo, Roberto Zanino   +2 more
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, Alessandro Del Nevo, Emanuela Martelli   +2 more
exaly   +5 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, Alessandro Del Nevo, Emanuela Martelli   +2 more
exaly   +2 more sources

Study of EU DEMO WCLL breeding blanket and primary heat transfer system integration

Fusion Engineering and Design, 2018
Abstract The Water-Cooled Lithium Lead breeding blanket is a candidate option for the realization of European DEMO power plant. One of the main functions of the breeding blanket is to recover the thermal power from the first wall and the breeding zone and to drive it to the Primary Heat Transfer System.
Caruso G, Alessandro Del Nevo, Emanuela Martelli   +2 more
exaly   +5 more sources