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Corrosion/Erosion Resistance of Ultimet\256 R31233 in a Simulated Feed for a Radioactive Vitrification Facility [electronic resource].

Published
Washington, D.C. : United States. Dept. of Energy, 1999.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Additional Creators
United States. Department of Energy. Savannah River Site, United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
Corrosion, erosion and corrosion/erosion tests were performed to evaluate the performance of nickel and cobalt based alloys in a simulated sludge/borosilicate frit slurry representative of the feed preparation system for a radioactive waste vitrification facility. Alloys tested included Type 304L stainless steel, Hastelloy\256 C-276, Stellite\256 6B, and Ultimet\256. Testing indicated that Ultimet\256 had improved wear resistance and similar corrosion resistance compared to Hastelloy\256 C-276 in the simulated sludge/frit environment.
Report Numbers
E 1.99:wsrc-ms-98-00655
wsrc-ms-98-00655
Subject(s)
Other Subject(s)
Note
Published through SciTech Connect.
05/21/1999.
"wsrc-ms-98-00655"
"DE00007523"
American Ceramics Society 101th Annual Meeting, Indianapolis, IN (USA), 27-28 Apr 1999.
Imrich, K.J.
Funding Information
AC09-96SR18500
View MARC record | catkey: 14457113