Results 271 to 280 of about 38,324 (298)
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A STUDY OF PERMEATION BARRIERS FOR Pb17Li BREEDING BLANKETS
1991Coatings on the surface in contact with Pb17Li can significantly decrease tritium permeation rate through structural steels and tritium inventory in the blanket. For this purpose, compatibility tests of oxidized and aluminized 316L and 1.4914 steels have been carried out up to 500°C in stagnant anisothermal Pb17Li.
A. Terlain +3 more
openaire +1 more source
Status of maturation of critical technologies and systems design: Breeding blanket
Fusion Engineering and Design, 2022Frederik Arbeiter +2 more
exaly
A Hydrogen Sensor for Liquid-Metal Breeding Blankets
2015In HCLL (Helium Cooled Lithium Lead) blanket for ITER fusion reactor, an efficient management operation of tritium is necessary, in order to minimize the release of tritium to the environment and to improve the economy of the overall balance of the reactor tritium inventory. In this context, optimization techniques for the measurement of tritium in the
NICOLOTTI, IURI +3 more
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Mechanical support concept of the DEMO breeding blanket
Fusion Engineering and Design, 2021Christian Bachmann +2 more
exaly
An overview of the EU breeding blanket design strategy as an integral part of the DEMO design effort
Fusion Engineering and Design, 2019L V Boccaccini +2 more
exaly
Breeding Blanket Modules testing in ITER: An international program on the way to DEMO
Fusion Engineering and Design, 2006V Chuyanov, R Lasser
exaly
Advancements in DEMO WCLL breeding blanket design and integration
International Journal of Energy Research, 2018Emanuela Martelli +2 more
exaly
A new HCPB breeding blanket for the EU DEMO: Evolution, rationale and preliminary performances
Fusion Engineering and Design, 2017Francisco A Hernández +2 more
exaly
Functional materials for breeding blankets—status and developments
Nuclear Fusion, 2017S. Konishi +6 more
openaire +1 more source