Recent progress in developing a feasible and integrated conceptual design of the WCLL BB in EUROfusion project
Sign Up to like & getrecommendations! Published in 2019 at "Fusion Engineering and Design"
DOI: 10.1016/j.fusengdes.2019.03.040
Abstract: Abstract The water-cooled lithium-lead breeding blanket is in the pre-conceptual design phase. It is a candidate option for European DEMO nuclear fusion reactor. This breeding blanket concept relies on the liquid lithium-lead as breeder-multiplier, pressurized… read more here.
Keywords: water; lithium lead; conceptual design; breeding blanket ... See more keywords
Parametric study of the influence of First Wall cooling water on the Water Cooled Lithium Lead Breeding Blanket nuclear response
Sign Up to like & getrecommendations! Published in 2019 at "Fusion Engineering and Design"
DOI: 10.1016/j.fusengdes.2019.03.105
Abstract: Abstract In the framework of EUROfusion Work Package International Cooperation R&D activities, a close collaboration has been started among University of Palermo, ENEA Brasimone and ENEA Frascati for the development of the Water Cooled Lithium… read more here.
Keywords: nuclear response; water cooled; cooled lithium; water ... See more keywords
Corrosion tests of multi-layer ceramic coatings in liquid lithium-lead
Sign Up to like & getrecommendations! Published in 2020 at "Fusion Engineering and Design"
DOI: 10.1016/j.fusengdes.2020.111874
Abstract: Abstract Tritium permeation through structural materials in fusion reactor blanket systems is a critical issue from the viewpoints of fuel loss and radiological safety. Ceramic coatings have been investigated to prevent tritium permeation; however, corrosion… read more here.
Keywords: lithium lead; multi layer; ceramic coatings; corrosion ... See more keywords
Lithium-lead corrosion behavior of erbium oxide, yttrium oxide and zirconium oxide coatings fabricated by metal organic decomposition
Sign Up to like & getrecommendations! Published in 2018 at "Journal of Nuclear Materials"
DOI: 10.1016/j.jnucmat.2018.06.021
Abstract: Abstract Tritium permeation through and corrosion of structural materials are critical issues in fusion reactor liquid lithium-lead blanket concepts from the viewpoints of an efficient fuel cycle, higher operation rates, and radiological safety. In this… read more here.
Keywords: erbium oxide; yttrium oxide; oxide coatings; oxide yttrium ... See more keywords
Structural and optical properties of samarium doped lithium lead borate glasses
Sign Up to like & getrecommendations! Published in 2019 at "Materials Research Express"
DOI: 10.1088/2053-1591/ab0768
Abstract: Sm3+ doped LPB (lithium lead borate) glass system were synthesised by conventional melt quenching technique. The non-crystalline behaviour of the glass system were characterised by x-ray diffraction technique. The physical parameters of prepared glass sample… read more here.
Keywords: lithium lead; optical properties; lead borate; range ... See more keywords
Neutronic Assessments towards a Novel First Wall Design for a Stellarator Fusion Reactor with Dual Coolant Lithium Lead Breeding Blanket
Sign Up to like & getrecommendations! Published in 2023 at "Energies"
DOI: 10.3390/en16114430
Abstract: The Stellarator Power Plant Studies Prospective R&D Work Package in the Eurofusion Programme was settled to bring the stellarator engineering to maturity, so that stellarators and particularly the HELIAS (HELical-axis Advanced Stellarator) configuration could be… read more here.
Keywords: breeding blanket; dual coolant; blanket; stellarator ... See more keywords