Results 21 to 30 of about 2,976 (267)
Research on Neutronics/Thermal-hydraulics Coupling Effect of CFETR Blanket
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
Fusion Blanket Inherent Safety Assessment [PDF]
Fusion has significant potential safety advantages. There is a strong incentive for designing fusion plants to ensure that inherent safety will be achieved. Accordingly, both the Tokamak Power Systems Studies and MINIMARS have identified inherent safety as a design goal.
Sze, D.K., Jung, J., Cheng, E.T.
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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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Blanket materials for dt fusion reactors [PDF]
Abstract This paper presents an overview of the critical materials issues that must be considered in the development of a tritium breeding blanket for a tokamak fusion reactor that operates on the D-T-Li fuel cycle. The primary requirements of the blanket system are identified and the important criteria that must be considered in the development of ...
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Neutronic analysis of effects of inboard materials on the size of a tokamak fusion reactor
The effects of inboard materials on the size of a tokamak fusion reactor were studied based on reactor system parameters determined through a coupled analysis of tokamak systems and neutron transport. With an inboard blanket, the shielding capability was
B.G. Hong, W. Cho
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Specifically engineered heavy liquid metals are proposed as candidate coolants and tritium breeders for advanced nuclear applications. Understanding the wetting behaviours of these liquids on relevant substrate configurations is crucial to tackle the ...
Abhishek Saraswat +3 more
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Applicability Analysis of Energy Storage Techniques for CFETR Fusion Power Plant
[Introduction] The power output of China Fusion Engineering Test Reactor (CFETR) is periodic, which can not directly meet the stable and continuous input requirements of conventional power generation equipment. CFETR fusion power plant needs to integrate
Zhanpeng LIANG +3 more
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The qualification and validation of nuclear technologies are daunting tasks for fusion demonstration (DEMO) and power plants. This is particularly true for advanced designs that involve harsh radiation environment with 14 MeV neutrons and high ...
Laila El-Guebaly +3 more
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The investigation of the neutronic responses of components in the K-DEMO
The neutronic response of consisting materials of the Korean fusion DEMOnstration reactor (K-DEMO) in its fusion neutron environment is a crucial consideration factor from the conceptual design stage of the K-DEMO.
Byung Chul Kim
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ABSTRACT Introduction Bloodstream infections due to repeated vascular access (VA) puncture and circuit connections remain major concerns in hemodialysis. Therefore, we examined current practices for glove, disinfectant, and personal protective equipment (PPE) use according to VA type in national university hospitals in Japan.
Aiko Yamada +6 more
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