Results 311 to 320 of about 138,513 (347)
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Transient Tritium Transport in a Solid Breeder Blanket
Nuclear Technology - Fusion, 1983A transient tritium permeation model is developed based on a simplified conceptual DT-fueled fusion reactor design. The major design features in the model are a solid breeder blanket, a low pressure purge gas in the blanket and a high pressure helium primary coolant.
D. R. Hanchar, M. S. Kazimi
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Testing needs and experiments for solid breeder blankets
Journal of Nuclear Materials, 1986Most of the critical issues for solid breeder blankets are related to the tritium and thermomechanical behavior of the solid breeder and multiplier. A major contributor to this uncertainty is the lack of definition of a preferred material, microstructure and form.
P. Gierszewski, R. Puigh
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Tritium Recovery from a Solid Breeder Demo Blanket
Fusion Technology, 1995The main task of a Tritium Extraction System (TES) for a helium cooled Li{sub 4}SiO{sub 4} DEMO blanket is the tritium recovery from a purge gas stream. On the basis of several TES proposals published for a NET/ITER solid breeder blanket, a new concept has been developed which is especially appropriate to cope with large purge gas streams.
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Towards Multiphysics Simulations of Fusion Breeder Blankets
International Conference on Physics of Reactors 2022 (PHYSOR 2022), 2022Helen Brooks +2 more
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Fusion Breeder Blanket Tritium Extraction Systems
Pacific Basin Nuclear Conference 2024 (PBNC)Chase Taylor +4 more
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Pre-conceptual design of an encapsulated breeder commercial blanket for the STEP fusion reactor
Fusion engineering and design, 2021J. Fradera +8 more
semanticscholar +1 more source
Feasible Chemical Forms for Thorium Breeder Blanket
Industrial & Engineering Chemistry, 1957M. H. Lietzke, R. W. Stoughton
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Progress on design and related R&D activities for the water-cooled breeder blanket for CFETR
Theoretical and Applied Mechanics Letters, 2019Songlin Liu, Xiaoman Cheng, Lei Chen
exaly

