Results 61 to 70 of about 1,038 (160)
Nuclear Materials and Energy, 2022 Tritium self-sufficiency is a key requirement for future fusion power plants. Therefore, it will be necessary to minimize tritium losses to the surrounding systems, such as the tritium breeding modules, plasma-facing components, cooling system, etc ...
R. Arredondo +4 more
doaj +1 more source
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 ...
Martelli, Emanuela +3 more
openaire +1 more source
, 2019 This paper presents the analyses performed within the SAE (Safety and Environment) project of EUROfusion/PPPT aimed at providing up-to-date estimates of the activity inventories and the decay heat generation in the WCLL.
Stankunas G., Moro F., Tidikas A.
core +1 more source
Dose rate evaluation in the technical premises of the demo fusion reactor using the serpent Monte Carlo code [PDF]
Nuclear Technology and Radiation ProtectionThis 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
Antropoloji, 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
ITER Water Cooled Lithium Lead Test Blanket System transient thermal-hydraulic analysis
Nuclear FusionThe planned experimental activities of the ITER Test Blanket Module (TBM) program will be a key step in understanding the physics and technologies required for tritium breeding blankets, which are essential for achieving tritium self-sufficiency in a ...
Tommaso Glingler +9 more
doaj +1 more source
MHD flow and heat transfer in model geometries for WCLL blankets
Fusion Engineering and Design, 2017 Abstract In the water cooled lead lithium (WCLL) blanket liquid lead lithium PbLi is used as breeder, neutron multiplier, and as heat transfer medium. The released heat is removed by water that flows at a pressure of 155 bar through cooling pipes immersed in the liquid-metal pool.
Bühler, L., Mistrangelo, C.
openaire +2 more sources
Main Nuclear Responses of the DEMO Tokamak with Different In-Vessel Component Configurations
Applied SciencesResearch 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
Nuclear 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
Neutronics Simulations for DEMO Diagnostics. [PDF]
Sensors (Basel), 2023 Luís R +13 more
europepmc +1 more source