Results 61 to 70 of about 933 (168)

MHD pressure drop estimate for the WCLL in-magnet PbLi loop

open access: yesFusion Engineering and Design, 2020
Abstract In the Water-Cooled Lithium Lead (WCLL) blanket, the eutectic alloy lithium-lead (PbLi) is used as tritium breeder and carrier, neutron multiplier, and heat transfer medium. The PbLi hydraulic loop section in the range of the reactor field coils, which includes the blanket and a non-negligible length of the connection pipes, is affected by ...
Alessandro Tassone   +4 more
openaire   +1 more source

Computational MHD analyses in support of the design of the WCLL TBM breeding zone

open access: yesFusion Engineering and Design, 2021
Abstract The Water-Cooled Lithium Lead (WCLL) is a blanket concept pursued in the framework of Test Blanket Module (TBM) campaign in ITER. Even if the liquid metal is circulated slowly in the component, magnetohydrodynamic (MHD) pressure losses are still expected to be significant.
Tassone, Alessandro, Caruso, Gianfranco
openaire   +2 more sources

Dose rate evaluation in the technical premises of the demo fusion reactor using the serpent Monte Carlo code [PDF]

open access: yesNuclear Technology and Radiation Protection
This paper presents a dose rate assessment within the DEMO fusion reactor's auxiliary premises, focusing on activated water and Activated Corrosion Products as primary radiation sources.
Sereda Svitlana   +4 more
doaj   +1 more source

Biology and anthropology before and after Bologna

open access: yesAntropoloji, 2004
The siıuition of ıhe teochin^ of Anthropûtogy is hî^hly variANo in Europc ahhough a nujoıiiy is followinj tbî sıruciun; 3 tuchek* level +2 nuyçr IcvcI +3 pItD.
Charles Susanne
doaj   +1 more source

Main Nuclear Responses of the DEMO Tokamak with Different In-Vessel Component Configurations

open access: yesApplied Sciences
Research and development of the DEMOnstration power plant (DEMO) breeder blanket (BB) has been performed in recent years based on a predefined DEMO tritium breeding ratio (TBR) requirement, which determines a loss of wall surface due to non-breeding in ...
Jin Hun Park, Pavel Pereslavtsev
doaj   +1 more source

High heat flux limits of the fusion reactor water-cooled first wall

open access: yesNuclear Engineering and Technology, 2019
The water-cooled WCLL blanket is one of the possible candidates for the blanket of the fusion power reactors. The plasma-facing first wall manufactured from the reduced-activation ferritic-martensitic steel Eurofer97 will be cooled with water at a ...
Pavel Zacha, Slavomir Entler
doaj   +1 more source

MHD and heat transfer analyses in PbLi radial channels for the EUROfusion WCLL breeding blanket

open access: yes, 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.
Alessandro Del Nevo   +7 more
core  

Number of channels involved following a break in the EU DEMO HCPB and WCLL BB FW

open access: yes, 2020
Excel file reporting the number of involved FW channels following a break in the FW for the EU DEMO HCPB and WCLL Breeding Blanket concepts. The file also reports the resulting flow area. Different break sizes are assumed: 0.01 m2, 0.1 m2 (small breaks),
Antonio Froio
core   +1 more source

Neutronics Simulations for DEMO Diagnostics. [PDF]

open access: yesSensors (Basel), 2023
Luís R   +13 more
europepmc   +1 more source

Home - About - Disclaimer - Privacy