Results 11 to 20 of about 490,328 (214)

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   +3 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

Tritium breeding and activation in the cascade reactor [PDF]

open access: yes, 1983
Cascade is an inertial fusion reactor that uses circulating Li/sub 2/O pellets as a coolant and tritium breeding medium. The pellets flow through a horizontal rotating vessel, and they are held against the vessel wall by centrifugal force. Three wall designs were considered: a steel shell and a SiC shell prestressed by Al or steel cables.
Blink, James A.
openaire   +4 more sources

Tritium Breeding Ceramics for Nuclear Fusion [PDF]

open access: yes
Tritium and deuterium are widely considered as fuel for fusion power plants. While deuterium is quite abundant in nature, tritium needs to be “bred” from lithium in a neutron reaction. Hence, for the breeding blanket development of the International Thermonuclear Experimental Reactor (ITER) and the DEMOnstration power plant (DEMO), the development of ...
Leys, Julia   +2 more
openaire   +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   +1 more source

Effect of annealing on microstructure and thermal conductivity of Li2TiO3 and Li4SiO4

open access: yesNuclear Materials and Energy, 2022
Li2TiO3 and Li4SiO4 are considered as candidate tritium breeding materials due to its excellent physical, chemical and tritium release performance. Thermal conductivities of solid tritium breeding materials are determined by microstructure, sintering ...
Baolong Ji   +6 more
doaj   +1 more source

Multiphysics Optimization for First Wall Design Enhancement in Water-Cooled Breeding Blankets

open access: yesNuclear Materials and Energy, 2021
The commercial feasibility of the first fusion power plant generation adopting D-T plasma is strongly dependent upon the self-sustainability in terms of tritium fuelling. Within such a kind of reactor, the component selected to house the tritium breeding
Ruggero Forte   +3 more
doaj   +1 more source

HCCR breeding blankets optimization by changing neutronic constrictions

open access: yesNuclear Engineering and Technology, 2021
The neutronic analysis of Helium Cooled Ceramic Reflector (HCCR) breeding blankets has been performed using the 3D Monte Carlo code MCNPX and ENDF nuclear data library.
R. Zadfathollah Seighalani   +2 more
doaj   +1 more source

Impact of blanket material and configuration on the size of a tokamak fusion reactor

open access: yesNuclear Materials and Energy, 2021
On the basis of the Korean fusion roadmap, conceptual design of the DEMO and R&D on the breeding blanket are ongoing. This article addresses the impact of blanket material and configuration on the tritium breeding, shielding characteristics, and ...
Bong Guen Hong
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

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