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Sodium Diffusion in the Nuclear Waste Glass GP 98/12
Author(s) -
Thomas Michael P.,
Matzke Hj.
Publication year - 1989
Publication title -
journal of the american ceramic society
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.9
H-Index - 196
eISSN - 1551-2916
pISSN - 0002-7820
DOI - 10.1111/j.1151-2916.1989.tb05969.x
Subject(s) - borosilicate glass , diffusion , radioactive waste , enthalpy , materials science , tracer , radioactive tracer , base (topology) , atmospheric temperature range , sodium , range (aeronautics) , analytical chemistry (journal) , vitrification , radiochemistry , chemical engineering , chemistry , nuclear chemistry , thermodynamics , composite material , metallurgy , chromatography , nuclear physics , mathematical analysis , physics , mathematics , engineering
The diffusion of 22 Na was measured in the nuclear waste borosilicate glass GP 98/12 in the temperature range of 350° to 450°C. The boundary condition of a thin initial tracer layer and serial sectioning were employed to measure the diffusion profiles. The activation enthalpy was found to be 1.08 eV. A parallel experiment with the base glass VG 98/12 not containing added (chemically simulated, inactive) waste showed that Na diffusion does not vary significantly when adding the waste.