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Integrated Corrosion Facility for long-term testing of candidate materials for high-level radioactive waste containment [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
4 pages : digital, PDF file
Additional Creators
Lawrence Livermore National Laboratory, United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
A long-term-testing facility, the Integrated Corrosion Facility (I.C.F.), is being developed to investigate the corrosion behavior of candidate construction materials for high-level-radioactive waste packages for the potential repository at Yucca Mountain, Nevada. Corrosion phenomena will be characterized in environments considered possible under various scenarios of water contact with the waste packages. The testing of the materials will be conducted both in the liquid and high humidity vapor phases at 60 and 90°C. Three classes of materials with different degrees of corrosion resistance will be investigated in order to encompass the various design configurations of waste packages. The facility is expected to be in operation for a minimum of five years, and operation could be extended to longer times if warranted. A sufficient number of specimens will be emplaced in the test environments so that some can be removed and characterized periodically. The corrosion phenomena to be characterized are general, localized, galvanic, and stress corrosion cracking. The long-term data obtained from this study will be used in corrosion mechanism modeling, performance assessment, and waste package design. Three classes of materials are under consideration. The corrosion resistant materials are high-nickel alloys and titanium alloys; the corrosion allowance materials are low-alloy and carbon steels; and the intermediate corrosion resistant materials are copper-nickel alloys.
Report Numbers
E 1.99:ucrl-jc--118689
E 1.99: conf-950570--3
conf-950570--3
ucrl-jc--118689
Subject(s)
Other Subject(s)
Note
Published through SciTech Connect.
10/01/1994.
"ucrl-jc--118689"
" conf-950570--3"
"DE95005921"
International high-level radioactive waste management conference: progress toward understanding, Las Vegas, NV (United States), 1-5 May 1995.
McCright, R.D.; Estill, J.C.; Gdowski, G.E.; Dalder, E.N.C.
Funding Information
W-7405-ENG-48
View MARC record | catkey: 14113797