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Safety and environmental advantages of using tritium-lean targets for inertial fusion [electronic resource].

Published
Washington, D.C : United States. Dept. of Energy. Office of the Assistant Secretary for Defense Programs, 1999.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description
669 Kilobytes pages : digital, PDF file
Additional Creators
Lawrence Livermore National Laboratory, United States. Department of Energy. Office of the Assistant Secretary for Defense Programs, and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
While traditional inertial fusion energy target designs typically use equimolar portions of deuterium and tritium and have areal densities (ρr) of ≈ 3 g/cm², significant safety and environmental (S and E) advantages may be obtained through the use of high-density (ρr ≈ 10 g/cm²) targets with tritium components as low as 0.5%. Such targets would absorb much of the neutron energy within the target and could be self-sufficient from a tritium breeding point of view. Tritium self-sufficiency within the target would free target chamber designers from the need to use lithium-bearing blanket materials, while low inventories within each target would translate into low inventories in target fabrication facilities. Absorption of much of the neutron energy within the target, the extremely low tritium inventories, and the greatly moderated neutron spectrum, make ''tritium-lean'' targets appear quite attractive from an S and E perspective.
Report Numbers
E 1.99:ucrl-jc-134830
E 1.99: at5015032
at5015032
ucrl-jc-134830
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Note
Published through SciTech Connect.
08/09/1999.
"ucrl-jc-134830"
" at5015032"
"AT5015032"
First International Conference on Inertial Fusion Sciences and Applications, Bordeaux (FR), 09/12/1999--09/17/1999.
Perkins, L J; Moir, R W; Logan, B G; Latkowski, J F; Meier, W R; Sanz, J; Arzeni, S.
Funding Information
W-7405-ENG-48
View MARC record | catkey: 14740353