Results 121 to 130 of about 1,096 (135)

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   +4 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, Ciro Alberghi, F Moro
exaly   +3 more sources

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

Fusion Engineering and Design, 2020
Francesco Edemetti, Emanuela Martelli, Alessandro Del Nevo   +2 more
exaly   +4 more sources

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 ...
D Flammini, M Angelone, Barbara Caiffi   +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, Emanuela Martelli, 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)
Candido, Luigi, Alberghi, Ciro, Arena, Pietro, Moro, Fabio, Noce, Simone, Utili, Marco, Zucchetti, Massimo   +6 more
openaire   +3 more sources

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, Mougenot, Jonathan, Hodille, Etienne, Charles, Y.   +3 more
openaire   +2 more sources

Modelling of tritium transport in WCLL breeding blankets: influence of neutron induced damage

, 2022
Dark, James, Delaporte-Mathurin, Rémi, Hodille, Etienne, Mougenot, Jonathan, Charles, Y., Grisolia, Christian   +5 more
openaire   +2 more sources

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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, Ivan Fernández-Berceruelo, Alessandro Tassone, Francesco Edemetti, Emanuela Martelli, Alessandro Del Nevo, David Rapisarda, Ángel Ibarra   +7 more
openaire   +1 more source

Conceptual design of a PAV-based tritium extractor for the WCLL breeding blanket of the EU DEMO: Effects of surface-limited vs. diffusion-limited modeling

, 2021
R. Bonifetto, Marco Utili, Domenico Valerio, R. Zanino   +3 more
openalex   +1 more source