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Materials considerations in accelerator targets [electronic resource].

Published:
Washington, D.C. : United States. Dept. of Energy, 1994.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description:
12 pages : digital, PDF file
Additional Creators:
Westinghouse Savannah River Company, United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information
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Summary:
Future nuclear materials production and/or the burn-up of long lived radioisotopes may be accomplished through the capture of spallation produced neutrons in accelerators. Aluminum clad-lead and/or lead alloys has been proposed as a spallation target. Aluminum was the cladding choice because of the low neutron absorption cross section, fast radioactivity decay, high thermal conductivity, and excellent fabricability. Metallic lead and lead oxide powders were considered for the target core with the fabrication options being casting or powder metallurgy (PM). Scoping tests to evaluate gravity casting, squeeze casting, and casting and swaging processes showed that, based on fabricability and heat transfer considerations, squeeze casting was the preferred option for manufacture of targets with initial core cladding contact. Thousands of aluminum clad aluminum-lithium alloy core targets and control rods for tritium production have been fabricated by coextrusion processes and successfully irradiated in the SRS reactors. Tritium retention in, and release from the coextruded product was modeled from experimental and operational data. Newly produced tritium atoms were trapped by lithium atoms to form a lithium tritide. The effective tritium pressure required for trap or tritide stability was the equilibrium decomposition pressure of tritium over a lithium tritide-aluminum mixture. The temperature dependence of tritium release was determined by the permeability of the cladding to tritium and the local equilibrium at the trap sites. The model can be used to calculate tritium release from aluminum clad, aluminum-lithium alloy targets during postulated accelerator operational and accident conditions. This paper describes the manufacturing technologies evaluated and presents the model for tritium retention in aluminum clad, aluminum-lithium alloy tritium production targets.
Report Numbers:
E 1.99:wsrc-ms--94-0383
E 1.99: conf-9407103--2
conf-9407103--2
wsrc-ms--94-0383
Subject(s):
Other Subject(s):
Note:
Published through SciTech Connect.
08/01/1994.
"wsrc-ms--94-0383"
" conf-9407103--2"
"DE94015832"
International conference on accelerator-driven transmutation technologies and applications,Las Vegas, NV (United States),25 Jul - 1 Aug 1994.
Iyer, N.C.; Peacock, H.B. Jr.; Louthan, M.R. Jr.
Funding Information:
AC09-89SR18035
View MARC record | catkey: 14458362