Results 21 to 30 of about 2,976 (267)

Research on Neutronics/Thermal-hydraulics Coupling Effect of CFETR Blanket

open access: yesYuanzineng 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  

Fusion Blanket Inherent Safety Assessment [PDF]

open access: yesFusion Technology, 1986
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.
openaire   +1 more source

Design and simulation of a blanket module with high efficiency cooling system of tokamak focused on DEMO reactor

open access: yesNuclear 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
doaj   +1 more source

Blanket materials for dt fusion reactors [PDF]

open access: yesJournal of Nuclear Materials, 1981
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 ...
openaire   +1 more source

Neutronic analysis of effects of inboard materials on the size of a tokamak fusion reactor

open access: yesNuclear Materials and Energy, 2021
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
doaj   +1 more source

Development of a Test Bed to Investigate Wetting Behaviours of High-Temperature Heavy Liquid Metals for Advanced Nuclear Applications

open access: yesLiquids
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
doaj   +1 more source

Applicability Analysis of Energy Storage Techniques for CFETR Fusion Power Plant

open access: yes南方能源建设, 2022
[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
doaj   +1 more source

TBM/MTM for HTS-FNSF: An Innovative Testing Strategy to Qualify/Validate Fusion Technologies for U.S. DEMO

open access: yesEnergies, 2016
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
doaj   +1 more source

The investigation of the neutronic responses of components in the K-DEMO

open access: yesNuclear Fusion, 2023
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
doaj   +1 more source

Infection Control Practices for Vascular Access Management in Hemodialysis: Results From a Nationwide Survey of Japanese National University Hospitals

open access: yesTherapeutic Apheresis and Dialysis, EarlyView.
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
wiley   +1 more source

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