Initial dissolution rate of a Japanese simulated high-level waste glass P0798 as a function of pH and temperature measured by using micro-channel flow-through test method
Author:
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
http://www.tandfonline.com/doi/pdf/10.1080/00223131.2012.669246
Reference27 articles.
1. J.K. Bates and M.J. Steindler, Alteration of nuclear waste glass by hydration, inScientific Basis for Nuclear Waste Management IV, D.G. Brookins, ed., Mat. Res. Soc. Symp. Proc., Vol. 15, 1983, pp. 83–90
2. Evaluation of the single-pass flow-through test to support a low-activity waste specification
3. Measurement of kinetic rate law parameters on a NaCaAl borosilicate glass for low-activity waste
4. Single-pass flow-through experiments on a simulated waste glass in alkaline media at 40°C.
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