Results 11 to 20 of about 525,516 (210)
The impact of design parameters on tritium breeding in a water cooled blanket for CFETR [PDF]
AIP AdvancesThe CFETR (China Fusion Engineering Test Reactor) is a major Chinese scientific project to design, build, and operate a next-generation tokamak nuclear fusion reactor.
Jie Li, Haiyan Yang, Jie Zhang
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Nuclear Engineering and TechnologyFusion reactors produce high-energy neutrons through the Deuterium-Tritium (DT) reaction. The long-term performance verification and structural integrity assessment of the breeding blanket under continuous plasma operation are essential for the ...
Hyoseong Gwon +3 more
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Exploratory tritium breeding performance study on a water cooled lead ceramic breeder blanket for EU DEMO using Serpent-2 [PDF]
Nuclear Materials and Energy, 2021 Innovative Water cooled Lead Ceramic Breeder (WLCB) blanket concepts are being developed at Karlsruhe Institute of Technology (KIT) to explore alternative options for the European demonstration fusion power plant (DEMO).
Yudong Lu +5 more
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Energies, 2021 A tritium breeding blanket (TBB) is an essential component in a fusion reactor, which has functions of tritium breeding, energy generation and neutron shielding.
Shen Qu +4 more
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Conceptual design of solid-type Pb x Li y eutectic alloy breeding blanket for CFETR
Nuclear Fusion, 2023 As a key component of the Chinese Fusion Engineering and Test Reactor (CFETR), the blanket is responsible for tritium breeding, neutron shielding and energy conversion.
K. Jiang, Q. Wu, L. Chen, S. Liu
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Neutronics Design of Tritium Breeding Blanket for Fusion Experimental Reactor [PDF]
Journal of Nuclear Science and Technology, 1983 Detailed neutronics analysis on a tokamak fusion experimental reactor was performed. Neutronics responses of components in the vacuum vessel of a swimming pool type reactor were calculated by Monte Carlo method considering toroidal geometry, asymmetrical torus cross section, and neutron source distribution in plasma.
MORI, Seiji +2 more
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Thermodynamic Performance of Ceramic Tritium Breeding Blanket Material [PDF]
Fusion Technology, 1986 Thermodynamic calculations have been made to compare the thermochemical performance of three candidate breeder blanket materials, Li/sub 2/O, LiAlO/sub 2/, and Li/sub 4/SiO/sub 4/. These calculations were done for the temperature range of 900 to 1300/sup 0/K and the oxygen activity range of 10/sup -25/ to 10/sup -5/.
Johnson, C. E., Fischer, A. K.
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Analysis of Coolant Purification Strategies for Tritium Control in DEMO Water Primary Coolant
Energies, 2023 A major objective of the European fusion program is the design of the DEMOnstration power plant named DEMO. Up to now, most fusion experiments have been dedicated to a plasma physics investigation while, in DEMO-oriented activities, large attention is ...
Vincenzo Narcisi +3 more
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Study on fusion blanket with ceramic solid as tritium breeding material [PDF]
Journal of Physics: Conference Series, 2021 Abstract Variation of solid ceramic breeding might be one of the excellent candidates in a fusion reactor. The LiAlO2, Li4SiO4, Li2O, and Li2ZrO3 show pretty good requirements in tritium breeding capability and thermodynamic behavior. Especially for LiAlO2 and Li2ZrO3, in which they could be possible to breed without neutron multiplying ...
I R Maemunah +3 more
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Frontiers in Energy Research, 2021 Tritium breeding blanket (TBB) is an essential component in a fusion reactor, which has functions of tritium breeding, energy generation, and neutron shielding.
Shen Qu +6 more
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