Impact of armor materials on tritium breeding ratio in the fusion reactor blanket
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference15 articles.
1. A simulation study of thermal breeding of tritium at low temperatures in a D–T fusion reactor blanket
2. Enhancing tritium breeding characteristics of a fusion reactor blanket
3. Neutronic and photonic analysis of the single box water-cooled lithium lead blanket for a DEMO reactor
4. Design studies on nuclear properties on the Flibe blanket for helical-type fusion reactor FFHR
5. ITER reference breeding blanket design
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1. Tritium breeding ratio optimization in simple multi-layer blanket with genetic algorithm;Fusion Engineering and Design;2024-05
2. Microstructure and Mechanical Properties of W–10Cr–0.5Y Alloy under Heavy Ion Irradiation;Physics of Atomic Nuclei;2023-12
3. GAMBL – A dual-cooled fusion blanket using SiC-based structures;Fusion Engineering and Design;2022-07
4. Experimental study on tritium breeding in water-cooled ceramic breeder blanket mock-up under D–T neutron irradiation conditions;Nuclear Fusion;2021-05-04
5. A neutronics probe ball method on tritium generation rate simulation for a nuclear fusion reactor blanket;Fusion Engineering and Design;2021-02
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