Results 221 to 230 of about 3,005 (266)

Fusion blankets-a comparative study

Journal of Fusion Energy, 1985
The Argonne National Laboratory conducted a study to develop a technically based rationale where an RandD program can be conducted. First, the development of a viable blanket for fusion is in itself a major feasibility issue, not just an engineering task.
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Aspects of Fusion Reactor Blankets

SAE Technical Paper Series, 1992
<div class="htmlview paragraph"><i>The blanket is the medium that allows the heat energy to be extracted from the fusion reactor as well as the breeding of tritium to be used in fuelling the plasma. The difficulty encountered in the design of this component lies in the inherent requirement not just to multiply and moderate the incoming ...
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Evaluation of candidate blanket materials for fusion reactor blanket applications

Journal of Nuclear Materials, 1984
Abstract This paper summarizes the primary candidate materials currently considered for major components, viz., structure, breeder, coolant, etc. Compatible combinations of materials that offer the most potential for satisfactory performance and the projected ranges of operating parameters are indicated. Critical properties of the candidate materials
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Fusion Breeder Blanket Design Considerations

Nuclear Technology - Fusion, 1983
The Fusion Breeder Program is a DOE funded program directed by Lawrence Livermore National Laboratory; the other participants in this hybrid fusion reactor design are TRW Company, GA Technologies Inc., Westinghouse Corporation, and Oak Ridge National Laboratory.
C. P. C. Wong, R. L. Creedon, I. Maya, K. R. Schultz   +3 more
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Optimal Use of Beryllium for Fusion Reactor Blankets

Fusion Technology, 1986
The 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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Development of advanced blanket materials for a solid breeder blanket of a fusion reactor

Nuclear Fusion, 2003
The design of an advanced solid breeding blanket in a DEMO reactor requires a tritium breeder and a neutron multiplier that can withstand high temperatures and high neutron fluences, and the development of such advanced blanket materials has been carried out by collaboration between JAERI, universities and industries in Japan.
H Kawamura, E Ishitsuka, K Tsuchiya, M Nakamichi, M Uchida, H Yamada, K Nakamura, H Ito, T Nakazawa, H Takahashi, S Tanaka, N Yoshida, S Kato, Y Ito   +13 more
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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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