Actions for Neutronic implications of lead-lithium blankets [electronic resource].

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Neutronic implications of lead-lithium blankets [electronic resource].

Published
Livermore, Calif : Lawrence Livermore National Laboratory, 1982.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description
Pages: 15 : digital, PDF file
Additional Creators
Lawrence Livermore National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
Lead-lithium alloys have been proposed for use in several conceptual blanket designs for both inertial and magnetic confinement fusion reactors. In most cases, Pb/sub 83/Li/sub 17/, a eutectic with a melting point of 235/sup 0/C, is the chosen composition. The primary reasons for using Pb/sub 83/Li/sub 17/ instead of Li as the tritium breeding material are the perceived safety advantages, low tritium solubility, and favorable neutronic characteristics. This paper describes the neutronic characteristics of Pb/sub 83/Li/sub 17/ blankets with emphasis on the enhanced neutron leakage through chamber ports and the degradation in blanket performance parameters that occurs as a result of the enhanced leakage.
Report Numbers
E 1.99:ucrl-87499
E 1.99: conf-820948-1
conf-820948-1
ucrl-87499
Subject(s)
Other Subject(s)
Note
Published through SciTech Connect.
08/01/1982.
"ucrl-87499"
" conf-820948-1"
"DE82021629"
12. symposium on fusion technology, Juelich, F.R. Germany, 13 Sep 1982.
Meier, W.R.
Funding Information
W-7405-ENG-48
View MARC record | catkey: 14755399