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Optimal Use of Beryllium for Fusion Reactor Blankets
Fusion Technology, 1986The use of beryllium as a neutron multiplier for fusion reactor blankets has been analyzed. The analysis has been performed based on designs for a helium-cooled ceramic breeder and a self-cooled li...
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Benchmark calculations for fusion blanket development
Radiation Effects, 1986Abstract Benchmark problems representing the leading fusion blanket concepts are presented. Benchmark calculations for self-cooled Li17Pb83 and helium-cooled blankets were performed. Multigroup data libraries generated from ENDF/B-IV and V files using the NJOY and AMPX processing codes with different weighting functions were used.
Mohamed E. Sawan, Edward T. Cheng
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Tritium in Fusion Power Reactor Blankets
Nuclear Technology, 1974Several related problems involving the recovery of tritium from the breeding blanket in fusion power reactors are considered. They include the use of stagnant lithium blankets, the use of lithium as a regenerable getter pump, and the use of breeder materials that are lithium intermetallic alloys. Transient tritium recovery rates during startup are also
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The Nuclear Performance of Fusion Reactor Blankets
Nuclear Applications and Technology, 1970The neutronic behavior of fusion reactor blankets is discussed, and transport-theory calculations are presented for two blanket designs.
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HIP technologies for fusion reactor blankets fabrication
Fusion Engineering and Design, 2000The benefit of HIP techniques applied to the fabrication of fusion internal components for higher performances, reliability and cost savings are emphasized. To demonstrate the potential of the techniques, design of new blankets concepts and mock-ups fabrication are currently performed by CEA.
G Le Marois +3 more
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Tritium technology for blankets of fusion power plants
Fusion Engineering and Design, 2000Thermonuclear fusion power stations based on the deuterium-tritium reaction require breeding blankets to produce the tritium (T) fuel consumed in the plasma. This paper resumes the state-of-the-art of the T related technology from the initial T production in the lithium-bearing breeder material to a T stream which is ready for re-injection into the ...
Fütterer, M. A. +7 more
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Fusion First-Wall/Blanket Materials
1981At first sight it might appear somewhat incongruous that a discussion on CTR materials should be included in what is admittedly a fission-reactordominated work. However, the intent here is not to embark on a detailed discussion of CTR materials development (which could fill a book in itself) but, rather, to continue the theme developed in preceding ...
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Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan, 2004
Satoshi KONISHI +7 more
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Satoshi KONISHI +7 more
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Confinement of a fusion plasma by a cold gas blanket
Canadian Journal of Physics, 1977The particle end losses from a linear magnetic fusion reactor can be suppressed by establishing an ablation front in a cold gas blanket. The power density W(W/cm2) to drive the thermal front may be drawn from inside (energy end losses) or outside (auxiliary heating). With W below 109 W/cm2 and a D–T blanket the particle outflow is retarded.
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