Results 21 to 30 of about 1,114 (183)

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

Modeling and analysis of the tritium fuel cycle for ARC- and STEP-class D-T fusion power plants

open access: yesNuclear Fusion, 2023
The limited tritium resources available for the first fusion power plants (FPPs) make fuel self-sufficiency and tritium inventory minimization leading issues in FPP design. This work builds on the model proposed by Abdou et al (2020 Nucl.
Samuele Meschini   +3 more
doaj   +1 more source

Neutronic Activity for Development of the Promising Alternative Water-Cooled DEMO Concepts

open access: yesApplied Sciences, 2023
An emerging breeding blanket that fulfills performance criteria, meets the safety requirements, and is reliable enough to meet the plant availability is a challenging issue that assumes complex studies involving numerous neutronic analyses based on the ...
Pavel Pereslavtsev   +3 more
doaj   +1 more source

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   +1 more source

Tritium Breeding and Direct Energy Conversion [PDF]

open access: yes, 1972
Tritium breeding and direct energy conversion are key technological problems in the development of practical fusion reactors. Lithium in some form is needed for tritium generation, but certain chemical problems must be overcome. Alternatives to lithium metal should be considered.
openaire   +3 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   +1 more source

Tritium Breeding in Fusion Reactors [PDF]

open access: yes, 1983
Key technological problems that influence tritium breeding in fusion blankets are reviewed. The breeding potential of candidate materials is evaluated and compared to the tritium breeding requirements. The sensitivity of tritium breeding to design and nuclear data parameters is reviewed.
openaire   +1 more source

Assessments of Tritium Breeding Requirements and Breeding Potential for the STARFIRE/Demo Design [PDF]

open access: yesNuclear Technology - Fusion, 1983
This paper presents assessments of tritium breeding requirements and breeding potential for the STARFIRE/DEMO design. The assessment of breeding requirement is described based on two design considerations; i.e., (1) tritium inventory and doubling requirement; and (2) computational uncertainties associated with the breeding calculation.
Jung, J., Abdou, M.
openaire   +1 more source

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

open access: yesAIP 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

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   +1 more source

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