Results 1 to 10 of about 3,228,998 (208)

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

open access: yesMachine Learning: Science and Technology, 2023
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,
P Mánek   +5 more
doaj   +8 more sources

Neutronics Perturbation Calculation Method Study of Solid Breeder Tritium Breeding Blanket for TBR Enhancement

open access: yesFrontiers in Energy Research, 2021
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   +6 more
doaj   +1 more source

Optimal Radial Build and Transmutation Properties of a Fusion-Based Transmutation Reactor with Molten Salt Coolants

open access: yesEnergies, 2022
The optimal shape of a fusion-based transmutation reactor with a molten salt coolant was determined by plasma physics, technology, and neutronic requirements.
Bong-Guen Hong
doaj   +1 more source

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

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   +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

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

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

Conceptual design of solid-type Pb x Li y eutectic alloy breeding blanket for CFETR

open access: yesNuclear Fusion, 2023
As a key component of the Chinese Fusion Engineering and Test Reactor (CFETR), the blanket is responsible for tritium breeding, neutron shielding and energy conversion.
K. Jiang, Q. Wu, L. Chen, S. Liu
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

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