Tritium Processing and Containment Technology for Fusion Reactors, Annual Report: July 1975-June 1976

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The hydrogen permeabilities of selected metals, alloys, and multiplex preparations that are of interest to fusion reactor technology are being characterized. A high-vacuum hydrogen-permeation apparatus has been constructed for this purpose. A program of studies has been initiated to develop design details for the tritium-handling systems of near-term fusion reactors. This program has resulted in a better definition of reactor-fuel-cycle and enrichment requirements and has helped to identify major research and development problems in the tritium-handling area. The design and construction of a 50-gallon lithium-processing test loop (LPTL) is well under way. Studies in support of this project are providing … continued below

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v, 42 p. : charts, tables

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Maroni, V. A.; Calaway, W. F.; Misra, B.; Van Deventer, E. H.; Wegton, J. R.; Yonco, R. M. et al. 1976?.

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The hydrogen permeabilities of selected metals, alloys, and multiplex preparations that are of interest to fusion reactor technology are being characterized. A high-vacuum hydrogen-permeation apparatus has been constructed for this purpose. A program of studies has been initiated to develop design details for the tritium-handling systems of near-term fusion reactors. This program has resulted in a better definition of reactor-fuel-cycle and enrichment requirements and has helped to identify major research and development problems in the tritium-handling area. The design and construction of a 50-gallon lithium-processing test loop (LPTL) is well under way. Studies in support of this project are providing important guidance in the selection of hardware for the LPTL and in the design of a molten-salt processing test section.

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v, 42 p. : charts, tables

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  • OCLC: 879878915
  • SuDoc Number: Y 3.AT 7:22/ANL-76-133
  • Report No.: ANL-76-133
  • Grant Number: W-31-109-Eng-38
  • Archival Resource Key: ark:/67531/metadc282937

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  • 1976?

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  • Aug. 31, 2015, 12:37 p.m.

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Thumbnail image of item number 1 in: 'Tritium Processing and Containment Technology for Fusion Reactors, Annual Report: July 1975-June 1976'.
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Maroni, V. A.; Calaway, W. F.; Misra, B.; Van Deventer, E. H.; Wegton, J. R.; Yonco, R. M. et al. Tritium Processing and Containment Technology for Fusion Reactors, Annual Report: July 1975-June 1976, report, 1976?; Argonne, Illinois. (https://digital.library.unt.edu/ark:/67531/metadc282937/: accessed May 30, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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