Results 231 to 240 of about 2,976 (267)

Benchmark calculations for fusion blanket development

Radiation Effects, 1986
Abstract 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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The Nuclear Performance of Fusion Reactor Blankets

Nuclear Applications and Technology, 1970
The neutronic behavior of fusion reactor blankets is discussed, and transport-theory calculations are presented for two blanket designs.
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Tritium in Fusion Power Reactor Blankets

Nuclear Technology, 1974
Several 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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HIP technologies for fusion reactor blankets fabrication

Fusion Engineering and Design, 2000
The 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, L Federzoni, P Bucci, P Revirand   +3 more
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Tritium technology for blankets of fusion power plants

Fusion Engineering and Design, 2000
Thermonuclear 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., Albrecht, H., Giroux, P., Glugla, M., Kawamura, H., Kveton, O. K., Murdoch, D. K., Sze, D. K.   +7 more
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Fusion First-Wall/Blanket Materials

1981
At 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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Tritium-producing blanket for fusion engineering facility

Fusion Engineering and Design, 1989
The usefulness of ITER to fusion development can be substantially increased if the design parameters and features are selected so as to maximize reactor relevance without significantly increasing the risk. One critical area in which reactor relevance and risk are major issues is the tritium-producing blanket.
A.R. Raffray, M.A. Abdou, M.S. Tillack, M.Z. Youssef, Y. Watanabe   +4 more
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Structural materials for fusion reactor blanket systems

Journal of Materials for Energy Systems, 1985
The blanket is one of the largest and most complex systems in a fusion power reactor. In a D-T fueled reactor the blanket system recovers the energy produced by the fusion reaction and provides for breeding and recovery of tritium for the fuel cycle.
E. E. Bloom, D. L. Smith
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Fusion Blanket Construction

Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan, 2004
Satoshi KONISHI, Akihiko KIMURA, Masato AKIBA, Hiroo NAKAMURA, Takuya NAGASAKA, Takeo MUROGA, Akira HASEGAWA, Hideki MATSUI   +7 more
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Confinement of a fusion plasma by a cold gas blanket

Canadian Journal of Physics, 1977
The 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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