Results 1 to 10 of about 571,720 (260)

Study on the effect of neutron shielding design on tritium breeding based on water-cooled ceramic blanket for CFETR

open access: yesAIP Advances, 2023
The Chinese Fusion Engineering Test Reactor (CFETR) is a magnetic confinement fusion reactor independently designed and developed by China, which is based on the ITER design experience.
Jie Li   +7 more
doaj   +2 more sources

Study on Multiphysics Coupling and Automatic Neutronic Optimization for Solid Tritium Breeding Blanket of Fusion Reactor

open access: yesEnergies, 2021
A tritium breeding blanket (TBB) is an essential component in a fusion reactor, which has functions of tritium breeding, energy generation and neutron shielding.
Shen Qu   +4 more
doaj   +2 more sources

Composition design and preparation of lithium lead titanate (Li2PbxTi1-xO3, 0.1 < x < 0.9): A novel tritium breeding ceramic

open access: yesNuclear Materials and Energy
In deuterium–tritium (D-T) fusion reactors, the design of tritium breeding materials plays very critical role in tritium self-sufficiency. Compared to materials like Li2O, Li2TiO3 has a weaker tritium breeding capability, because of the lower density of ...
Xinyu Gao   +5 more
doaj   +2 more sources

RFP-MSR Hybrid Reactor Model for Tritium Breeding and Actinides Transmutation

open access: yesEnergies
The studies on the development of fusion–fission hybrid reactors (FFHR) have gained consensus in recent years as an intermediate step before fusion energy.
Stefano Murgo   +9 more
doaj   +2 more sources

Conceptual design study of the tritium breeding unit for verifying the long-term performance of the breeding blanket

open access: yesNuclear Engineering and Technology
Fusion reactors produce high-energy neutrons through the Deuterium-Tritium (DT) reaction. The long-term performance verification and structural integrity assessment of the breeding blanket under continuous plasma operation are essential for the ...
Hyoseong Gwon   +3 more
doaj   +2 more sources

Fast regression of the tritium breeding ratio in fusion reactors [PDF]

open access: yesMachine Learning: Science and Technology, 2021
The tritium breeding ratio (TBR) is an essential quantity for the design of modern and next-generation D-T fueled nuclear fusion reactors. Representing the ratio between tritium fuel generated in breeding blankets and fuel consumed during reactor runtime,
Petr Mánek   +5 more
semanticscholar   +7 more sources

Annihilation kinetics of irradiation defects in promising tritium breeding pebbles

open access: yesNuclear Materials and Energy, 2021
Lithium-based tritium breeding materials will be adopted to produce tritium in the D-T fusion reactor. Li2TiO3 and Li4SiO4 pebbles have been proposed as candidates in water-cooled ceramic breeder blanket (WCCB) and helium-cooled ceramic breeder blanket ...
Baolong. Ji   +6 more
doaj   +2 more sources

Optimization of tritium breeding ratio in ARC reactor [PDF]

open access: yesFusion Engineering and Design, 2020
Abstract Affordable Robust Compact reactor is a conceptual design for a Tokamak conceived by Massachusetts Institute of Technology (MIT) researchers. The design of this tokamak is under development and update. One of the key parameters for fusion reactor power plants is the tritium breeding ratio (TBR), which has to guarantee the tritium self ...
S. Segantin   +4 more
semanticscholar   +3 more sources

Impact of Blanket Configuration on the Design of a Fusion-Driven Transmutation Reactor [PDF]

open access: yesInternational Journal of Renewable Energy Development, 2018
A configuration of a fusion-driven transmutation reactor with a low aspect ratio tokamak-type neutron source was determined in a self-consistent manner by using coupled analysis of tokamak systems and neutron transport.
Bong Guen Hong
doaj   +2 more sources

Preliminary assessment of tritium permeation and retention in the European Water Cooled Lithium Lead Test Blanket Module with TESSIM-X

open access: yesNuclear Materials and Energy, 2022
Tritium self-sufficiency is a key requirement for future fusion power plants. Therefore, it will be necessary to minimize tritium losses to the surrounding systems, such as the tritium breeding modules, plasma-facing components, cooling system, etc ...
R. Arredondo   +4 more
doaj   +1 more source

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