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in subjects: "Zirconium Compounds 700201* -- Fusion Power Plant Technology-- Blanket Engineering"  
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Fabrication, properties, and tritium recovery from solid breeder materials

Description: The breeding blanket is a key component of the fusion reactor because it directly involves tritium breeding and energy extraction, both of which are critical to development of fusion power. The lithium ceramics continue to show promise as candidate breeder materials. This promise was recognized by the International Thermonuclear Experimental Reactor (ITER) design team in its selection of ceramics as the first option for the ITER breeder material. Blanket design studies have indicated properties… more
Date: January 1, 1991
Creator: Johnson, C.E. (Argonne National Lab., IL (USA)); Kondo, T. (Japan Atomic Energy Research Inst., Tokyo (Japan)); Roux, N. (CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)); Tanaka, S. (Tokyo Univ. (Japan)) & Vollath, D. (Kernforschungszentrum Karlsruhe GmbH (Germany, F.R.))
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Partner: UNT Libraries Government Documents Department
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Performance of insulating materials for future fusion blankets

Description: Thermal conductivities of five candidate insulating materials were determined in the temperature range of 300 to 1000/sup 0/C in air, argon, and helium at 1 atm so that a comparison would be made with existing data. These were done in a non-nuclear environment. The test apparatus was a cylindrical shell cooled with water flowing through tubes attached to the shell. The insulation to be tested lined the inner part of the shell which was heated along the axis of the cylinder with a single electri… more
Date: January 1, 1979
Creator: Horn, F. L.; Fillo, J. A. & Powell, J. R.
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Partner: UNT Libraries Government Documents Department
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Fusion blanket high-temperature heat transfer

Description: Deep penetration of 14 MeV neutrons makes two-temperature region blankets feasible. A relatively low-temperature (approx. 300/sup 0/C) metallic structure is the vacuum/coolant pressure boundary, while the interior of the blanket, which is a simple packed bed of nonstructural material, operates at very high temperatures (>1000/sup 0/C). The water-cooled shell structure is thermally insulated from the steam-cooled interior. High-temperature steam can dramatically increase the efficiency of electr… more
Date: January 1, 1983
Creator: Fillo, J.A.
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Partner: UNT Libraries Government Documents Department
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Results of parametric neutronic studies for high-temperature blankets with breeding

Description: Previous conceptual studies have been extended to examine a wide range of possible blanket configurations. The overall goals of this study have been to achieve neutronically viable blanket combinations that obtain an average breeding ratio (BR) of at least 1.1 and a sufficiently high fraction of fusion energy, Q/sub FRAC//sup HI/ (20% HTE High Temperature Heat) in the HTE process steam. The present studies have converged on the most attractive blanket option. After a preliminary and a secondary… more
Date: January 1, 1981
Creator: Makowitz, H; Lazareth, O W; Powell, J R & Fillo, J A
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Partner: UNT Libraries Government Documents Department
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Fusion blankets for high-efficiency power cycles

Description: The efficiencies of blankets for fusion reactors are usually in the range of 30 to 40%, limited by the operating temperatures (500/sup 0/C) of conventional structural materials such as stainless steels. In this project two-zone blankets are proposed; these blankets consist of a low-temperature shell surrounding a high-temperature interior zone. A survey of nucleonics and thermal hydraulic parameters has led to a reference blanket design consisting of a water-cooled stainless steel shell around … more
Date: January 1, 1980
Creator: Usher, J L; Lazareth, O W; Fillo, J A; Horn, F L & Powell, J R
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Partner: UNT Libraries Government Documents Department
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BEATRIX: The international breeder materials exchange

Description: The BEATRIX experiment is an IEA-sponsored effort that involves the exchange of solid breeder materials and shared irradiation testing among research groups in several countries. The materials will be tested in both closed capsules (to evaluate material lifetime) and opened capsules (to evaluate purge-flow tritium recovery). Pre- and post-irradiation measurement of thermophysical and mechanical properties will also be carried out.
Date: January 1, 1986
Creator: Johnson, C. E.; Reuther, T. C. & Dupouy, J. M.
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Partner: UNT Libraries Government Documents Department
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Solid breeder materials

Description: Increased attention is being given to the consideration of lithium-containing ceramic materials for use as breeder blankets in fusion devices. These materials, e.g., Li/sub 2/O, ..gamma..-LiAlO/sub 2/, Li/sub 4/SiO/sub 4/, Li/sub 2/ZrO/sub 3/, etc., are attractive because of their inherent safety advantages. At present, there is a broad scope of laboratory and irradiation activities in force to provide the requisite data enabling selection of th prime-candidate solid breeder material.
Date: January 1, 1981
Creator: Johnson, C. E.; Clemmer, R. G. & Hollenber, G. W.
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Partner: UNT Libraries Government Documents Department
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Blanket options for high-efficiency fusion power

Description: The efficiencies of blankets for fusion reactors are usually in the range of 30 to 40%, limited by the operating temperatures (500/sup 0/C) of conventional structural materials such as stainless steels. In this project two-zone blankets are proposed; these blankets consist of a low-temperature shell surrounding a high-temperature interior zone. A survey of nucleonics and thermal hydraulic parameters has led to a reference blanket design consisting of a water-cooled stainless steel shell around … more
Date: January 1, 1980
Creator: Usher, J L; Lazareth, O W; Fillo, J A; Horn, F L & Powell, J R
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Fusion blanket for high-efficiency power cycles

Description: The efficiencies of blankets for fusion reactors are usually in the range of 30 to 40%, limited by the operating temperature (500/sup 0/C) of conventional structural materials such as stainless steels. In this project two-zone blankets are proposed; these blankets consist of a low-temperature shell surrounding a high-temperature interior zone. A survey of nucleonics and thermal hydraulic parameters has led to a reference blanket design consisting of a water-cooled stainless steel shell around a… more
Date: January 1, 1980
Creator: Usher, J. L.; Powell, J. R.; Fillo, J. A.; Horn, F. L.; Lazareth, O. W. & Taussig, R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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