Solution exchange corrosion testing with the glass-zeolite ceramic waste form in demineralized water at 90{degree}C.

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A ceramic waste form of glass-bonded zeolite is being developed for the long-term disposition of fission products and transuranic elements in wastes from the U.S. Department of Energy's spent nuclear fuel conditioning activities. Solution exchange corrosion tests were performed on the ceramic waste form and its potential base constituents of glass, zeolite 5A, and sodalite as part of an effort to qualify the ceramic waste form for acceptance into the Civilian Radioactive Waste Management System. Solution exchange tests were performed at 90 C by replacing 80 to 90% of the leachate with fresh demineralized water after set time intervals. The ... continued below

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11 p.

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Simpson, L. J. May 19, 1998.

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Description

A ceramic waste form of glass-bonded zeolite is being developed for the long-term disposition of fission products and transuranic elements in wastes from the U.S. Department of Energy's spent nuclear fuel conditioning activities. Solution exchange corrosion tests were performed on the ceramic waste form and its potential base constituents of glass, zeolite 5A, and sodalite as part of an effort to qualify the ceramic waste form for acceptance into the Civilian Radioactive Waste Management System. Solution exchange tests were performed at 90 C by replacing 80 to 90% of the leachate with fresh demineralized water after set time intervals. The results from these tests provide information about corrosion mechanisms and the ability of the ceramic waste form and its constituent materials to retain waste components. The results from solution exchange tests indicate that radionuclides will be preferentially retained in the zeolites without the glass matrix and in the ceramic waste form, with respect to cations like Li, K, and Na. Release results have been compared for simulated waste from candidate ceramic waste forms with zeolite 5A and its constituent materials to determine the corrosion behavior of each component.

Physical Description

11 p.

Notes

INIS; OSTI as DE00010812

Medium: P; Size: 11 pages

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  • 100th Annual Meeting of the American Ceramic Society, Cincinnati, OH (US), 05/03/1998--05/06/1998

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  • Report No.: ANL/CMT/CP-96491
  • Grant Number: W-31109-ENG-38
  • Office of Scientific & Technical Information Report Number: 10812
  • Archival Resource Key: ark:/67531/metadc622732

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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  • May 19, 1998

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  • June 16, 2015, 7:43 a.m.

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  • April 6, 2017, 7:37 p.m.

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Simpson, L. J. Solution exchange corrosion testing with the glass-zeolite ceramic waste form in demineralized water at 90{degree}C., article, May 19, 1998; Illinois. (digital.library.unt.edu/ark:/67531/metadc622732/: accessed November 18, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.