Exploratory tritium breeding performance study on a water cooled lead ceramic breeder blanket for EU DEMO using Serpent-2
Autor: | Yuan Hu, Minyou Ye, Yudong Lu, Guangming Zhou, Francisco A. Hernández, Jaakko Leppänen |
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Jazyk: | angličtina |
Rok vydání: | 2021 |
Předmět: |
Technology
Nuclear and High Energy Physics Neutron transport Materials Science (miscellaneous) Nuclear engineering TK9001-9401 Fusion power Blanket Coolant Breeder (animal) Nuclear Energy and Engineering visual_art Serpent-2 visual_art.visual_art_medium Neutronics Environmental science Nuclear engineering. Atomic power Neutron Tritium Ceramic Tritium breeding Water cooled Lead Ceramic Breeder ddc:600 |
Zdroj: | Nuclear Materials and Energy, Vol 28, Iss, Pp 101050-(2021) Nuclear materials and energy, 28, Art. Nr.: 101050 Nuclear Materials and Energy Lu, Y, Ye, M, Zhou, G, Hernández, F A, Leppänen, J & Hu, Y 2021, ' Exploratory tritium breeding performance study on a water cooled lead ceramic breeder blanket for EU DEMO using Serpent-2 ', Nuclear Materials and Energy, vol. 28, 101050 . https://doi.org/10.1016/j.nme.2021.101050 |
ISSN: | 2352-1791 |
DOI: | 10.1016/j.nme.2021.101050 |
Popis: | 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). Compared to the Helium Cooled Pebble Bed blanket (HCPB, which is one of the two driver blanket concepts of the European DEMO), Lead/ Lead-alloy is used as neutron multiplier instead of Be/Be-alloy and pressurized subcooled water is used as coolant instead of Helium in the WLCB. The tritium self-sufficiency is the vital function that a Breeding Blanket has to achieve. The absorption of neutrons by water leads to a decrease in the number of neutrons, so the requirement to improve the tritium breeding capacity of the water-cooled blankets is particularly prominent. The Monte Carlo neutron transport code Serpent-2 developed by VTT in Finland has already been benchmarked to be applicable to neutronics calculations in the fusion reactors in a previous study. In this paper, an exploratory TBR study on Water cooled Lead Ceramic Breeder Blanket is presented. |
Databáze: | OpenAIRE |
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