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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 ...
Stefano Segantin   +2 more
exaly   +6 more sources

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

open access: yesMachine Learning: Science and Technology, 2023
Abstract 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, the TBR depends on reactor geometry and material ...
Petr Mánek   +5 more
openaire   +7 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

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   +2 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

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

Tritium Breeding Capability of Water Cooled Ceramic Breeder Blanket With Different Container Designs

open access: yesFusion Engineering and Design, 2019
Water cooled ceramic breeder (WCCB) blankets have been regarded as a primary concept in Japan. We investigated the tritium breeding capability of a WCCB blanket with a cylindrical structure, an advantageous shape for withstanding high coolant pressure ...
Takanori Hirose   +2 more
exaly   +2 more sources

BABY 1L: first tritium breeding campaign results

open access: yesNuclear Fusion
Achieving tritium self-sufficiency is a critical challenge for future fusion power plants. The BABY 1 L experiment, part of the LIBRA project at MIT, aims to benchmark tritium breeding and release in molten salt breeder systems under deuterium–tritium ...
Rémi Delaporte-Mathurin   +10 more
doaj   +3 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

Effect of the various tritium breeding materials on the tritium breeding ratio in ARC fusion reactor

open access: yesInternational Journal of Energy Studies, 2023
This study deals with TBR (Tritium Breeding Ratio) performance of the four different types of molten salt (FLiBe, FLiNaK, FLiNaBe, FLiNaRb) which has four different Li-6 enrichment ratios (0%, 30%, 60%, 90%) Moreover, two different vacuum vessel materials (SiC composite and V4Cr4Ti alloy) have been used in ARC reactor geometry. In models with TBR ≥1.05,
Uğur Atalay, Güven Tunç
openaire   +3 more sources

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