Results 261 to 270 of about 42,805 (305)

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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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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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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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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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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Breeding blanket concepts for fusion and materials requirements

Journal of Nuclear Materials, 2002
This paper summarizes the design and performances of recent breeding blanket concepts and identifies the key material issues associated with them. An assessment of different classes of concepts is carried out by balancing out the potential performance of the concepts with the risk associated with the required material development.
Raffray, A. R., Akiba, M., Chuyanov, V., Giancarli, L., Malang, S.   +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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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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Exact perturbation theory for fusion blanket design

Annals of Nuclear Energy, 2019
Abstract This work presents a novel Monte Carlo methodology that calculates the response to composition perturbations in a fixed source problem. Known as exact perturbation theory (EPT), the methodology utilizes a collision history-based approach for fixed source problems implemented in the code SERPENT.
Alejandra Jolodosky, Manuele Aufiero, Massimiliano Fratoni   +2 more
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Magnetohydrodynamic coolant flows in fusion reactor blankets

Annals of Nuclear Energy, 1979
Abstract The magnetohydrodynamic flow of a liquid metal coolant through a square duct is modeled in three dimensions to study the development of the flow in the entry region of a fusion reactor blanket. The effect of various wall conductivity configurations on the heat transfer capability and pressure gradient requirements is also investigated.
S. Khan, J.N. Davidson
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