Conceptual design of a ceramic breeding blanket for laser fusion power plants with online tunable tritium breeding ratio based on a variable neutron reflector: Remarkable no need of isotopic enrichment
Author:
Funder
CONACYT
MINECO
EUROfusion Consortium
Madrid Region
Publisher
Elsevier BV
Subject
Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering
Reference22 articles.
1. Modelling the thermomechanical behaviour of the tungsten first wall in HiPER laser fusion scenarios;Garoz;Nucl. Fusion,2016
2. Neutronics and activation analysis of lithium-based ternary alloys in IFE blankets;Jolodosky;Fusion Eng. Des.,2016
3. Toward the ultimate goal of tritium self-sufficiency: technical issues and requirements imposed on ARIES advanced power plants;El-Guebaly;Fusion Eng. Des.,2009
4. Physics and technology conditions for attaining tritium self-sufficiency for the DT fuel cycle;Sawan;Fusion Eng. Des.,2006
5. A new approach for assessing the required tritium breeding ratio and startup inventory in future fusion reactors;Kuan;Fusion Sci. Technol.,1999
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1. Composition design and preparation of lithium lead titanate (Li2PbxTi1-xO3, 0.1 < x < 0.9): A novel tritium breeding ceramic;Nuclear Materials and Energy;2024-03
2. Future for inertial-fusion energy in Europe: a roadmap;High Power Laser Science and Engineering;2023
3. Study of the Effect of Two Phases in Li4SiO4–Li2SiO3 Ceramics on the Strength and Thermophysical Parameters;Nanomaterials;2022-10-20
4. Space Dependent Study of Fast Neutron Spectra and Tritium Production Rate in a Fusion Reactor Blanket of Li2O;Indian Journal of Pure & Applied Physics;2022-09-30
5. Preparation of Li2TiO3-Li4SiO4-Pb tritium breeding ceramic and its mechanical properties;Ceramics International;2022-09
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