Results 21 to 30 of about 42,805 (305)

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, Zaixin Li, Xiaoyu Wang, Xueren Wang, Kaiming Feng   +4 more
doaj   +1 more source

Three-dimensional thermal-hydraulics/neutronics coupling analysis on the full-scale module of helium-cooled tritium-breeding blanket

Nuclear Engineering and Technology, 2023
Blanket is of vital importance for engineering application of the fusion reactor. Nuclear heat deposition in materials is the main heat source in blanket structure.
Qiang Lian, Simiao Tang, Longxiang Zhu, Luteng Zhang, Wan Sun, Shanshan Bu, Liangming Pan, Wenxi Tian, Suizheng Qiu, G.H. Su, Xinghua Wu, Xiaoyu Wang   +11 more
doaj   +1 more source

The impact of design parameters on tritium breeding in a water cooled blanket for CFETR [PDF]

AIP Advances
The 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
doaj   +1 more source

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

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, Qiang Lian, Qiang Lian, Yu Liang, Haoyu Liao, Simiao Tang, Simiao Tang, Simiao Tang, Luteng Zhang, Luteng Zhang, Zaiyong Ma, Zaiyong Ma, Wan Sun, Wan Sun   +13 more
doaj   +1 more source

A Two-Way Neutronics/Thermal-Hydraulics Coupling Analysis Method for Fusion Blankets and Its Application to CFETR

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, Liangzhi Cao, Qingming He, Hongchun Wu, Wei Shen   +4 more
doaj   +1 more source

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
core   +1 more source

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  

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

Nuclear 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

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

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, R. Amrollahi, M. Zare, S. Fazelpour   +3 more
doaj   +1 more source

Conceptual design of the EU-DEMO dual coolant lithium lead equatorial module [PDF]

, 2016
© 20xx IEEE. Personal use of this material is permitted. Permission from IEEE must be obtained for all other uses, in any current or future media, including reprinting/republishing this material for advertising or promotional purposes, creating new ...
Fernández, I., González, M., Mas de les Valls Ortiz, Elisabet, Moreno Sierra, César, Moreno, C., Palermo, I., Rapisarda, David   +6 more
core   +3 more sources