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Status of Fusion Reactor Blanket Design [PDF]
Fusion Technology, 1986 This paper provides a brief review of the Blanket Comparison and Selection Study (BCSS)1 and an overview of more recent fusion reactor blanket design efforts.
Smith, D. L., Sze, D. K.
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A neutron diode for subcritical multistage multipliers with special reference in tritium breeding [PDF]
, 2016 This is a copy of the author 's final draft version of an article published in the Journal of fusion energy. The final publication is available at Springer via http://dx.doi.org/10.1007/s10894-015-0049-7In this paper the interaction between a magnetic ...
Arias Montenegro, Francisco Javier +1 more
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Considering for the blanket structure scheme of HCCB DEMO
Theoretical and Applied Mechanics Letters, 2019 : For the solid blanket concept of helium cooled ceramic breeder (HCCB) demonstration fusion power plant (DEMO), a feasible blanket structure with configuration 2×X is proposed as considering relatively low temperature limit of neutron multiplier ...
Zhou Zhao +4 more
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Frontiers in Energy Research, 2023 In fusion reactors, many blanket concepts are designed with water as a coolant to transfer high-density heat from the fusion reaction out of the reactor core.
Qiang Lian +13 more
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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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Energies, 2020 The China Fusion Engineering Test Reactor (CFETR) is a tokamak device to validate and demonstrate fusion engineering technology. In CFETR, the breeding blanket is a vital important component that is closely related to the performance and safety of the ...
Tao Dai +4 more
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Preliminary evaluation of the expansion system size for a pressurized gas loop: Application to a fusion reactor based on a helium-cooled blanket [PDF]
, 2017 Some considerations to preliminarily design the size of the Expansion Volume (EV) and the relief pipes for a Vacuum Vessel Pressure Suppression System, to be adopted in a fusion reactor based on a helium cooled blanket, are presented.
CARUSO, Gianfranco, NOBILI, MATTEO
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Research on Neutronics/Thermal-hydraulics Coupling Effect of CFETR Blanket
Yuanzineng kexue jishu, 2022 Chinese Fusion Engineering Test Reactor (CFETR) has been proposed to bridge the technology gap between the International Thermonuclear Experimental Reactor (ITER) and the Fusion Demonstration Reactor (DEMO). As the most crucial nuclear component, fusion
DAI Tao;CAO Liangzhi;HE Qingming;WU Hongchun
doaj
IFMIF suitability for evaluation of fusion functional materials [PDF]
, 2011 The International FusionMaterials Irradiation Facility (IFMIF) is a future neutron source based on the D-Li stripping reaction, planned to test candidate fusionmaterials at relevant fusion irradiation conditions.
A. García +25 more
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Nuclear Engineering and Technology, 2020 In this study, the neutronic calculation to obtain tritium breeding ratio (TBR) in a deuterium-tritium (D-T) fusion power reactor using Monte Carlo MCNPX is done. In addition, by using COMSOL software, an efficient cooling system is designed.
H. Sadeghi +3 more
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