Results 21 to 30 of about 967,607 (110)

Parametric study of density wave instability in parallel channels of a water-cooled blanket in a fusion reactor

open access: yesFrontiers 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
doaj   +1 more source

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  

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

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 Cooling of a Fusion Reactor

open access: yesEnergies, 2023
Nuclear fusion is the gateway to a whole new paradigm of energy and is a strong candidate for the decarbonization of electricity generation on a global scale.
Robert Beaufait, Ludger Fischer
doaj   +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

The Current Status of Fusion Reactor Blanket Thermodynamics

open access: yes, 1979
This report addresses the current status of fusion reactor blanket ...
Yonco, R. M.   +2 more
core   +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

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

Fusion blanket integral neutronics experiments [PDF]

open access: yes, 1979
The feasibility of conducting fusion blanket integral neutronics experiments at the Rotating Target Neutron Source-II (RTNS-II) accelerator facility and the Tokamak Fusion Test Reactor (TFTR) was investigated. RTNS-II recently became operational, and the
Green, L.
core  

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