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Displacement damage in the first structural wall of an inertial confinement fusion reactor : dependence on blanket design

Author
Meier, W. R.
Published
United States : [publisher not identified], 1984
Springfield, Va.: National Technical Information Service, [approximately 1984]
Physical Description
microfiche : negative ; 11 x 15 cm

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Summary
In this study we investigate how the design of the neutron blanket effects the displacement damage rate in the first structural wall (FSW) of an Inertial Confinement Fusion (ICF) reactor. Two generic configurations are examined; in the first, the steel wall is directly exposed to the fusion neutrons, whereas in the second, the steel wall is protected by inner blanket of lithium with an effective thickness of 1-m. The latter represents a HYLIFE-type design, which has been shown to have displacement damage rates an order of magnitude lower than unprotected wall designs. The two basic configurations were varied to show how the dpa rate changes as the result of (1) adding a Li blanket outside the FSW, (2) adding a neutron reflector (graphite) outside the FSW, and (3) changing the position of the inner lithium blanket relative to the FSW. The effects of neutron moderation in the compressed DT-target are also shown, and the unprotected and protected configurations compared.
Report Numbers
DE84015082; UCID-20121
Other Subject(s)
Collection
NTIS collection.
Note
DOE contract number: W-7405-ENG-48
OSTI Identifier 6712629
Research organization: Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States).
View MARC record | catkey: 47342943