The role of Al2O3 in the long-term corrosion stability of nuclear waste glasses

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The role of Al2O3 in the long-term corrosion stability of nuclear waste glasses. / Van Iseghem, Pierre; Amaya, Takayuki; Suzuki, Yasuhiro; Yamamoto, H.

In: Journal of Nuclear Materials, Vol. 190, 1992, p. 269-276.

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Harvard

Van Iseghem, P, Amaya, T, Suzuki, Y & Yamamoto, H 1992, 'The role of Al2O3 in the long-term corrosion stability of nuclear waste glasses', Journal of Nuclear Materials, vol. 190, pp. 269-276. https://doi.org/10.1016/0022-3115(92)90090-8

APA

Van Iseghem, P., Amaya, T., Suzuki, Y., & Yamamoto, H. (1992). The role of Al2O3 in the long-term corrosion stability of nuclear waste glasses. Journal of Nuclear Materials, 190, 269-276. https://doi.org/10.1016/0022-3115(92)90090-8

Vancouver

Author

Van Iseghem, Pierre ; Amaya, Takayuki ; Suzuki, Yasuhiro ; Yamamoto, H. / The role of Al2O3 in the long-term corrosion stability of nuclear waste glasses. In: Journal of Nuclear Materials. 1992 ; Vol. 190. pp. 269-276.

Bibtex - Download

@article{bf6db51d81294bd8bd34b455e44d890b,
title = "The role of Al2O3 in the long-term corrosion stability of nuclear waste glasses",
abstract = "The corrosion stability of borosilicate waste glasses has been investigated, as a function of the AlO1.5 (in balance with SiO2) content. The AlO1.5 content ranged from 6.7 to 18.2 mol{\%}. Surface area to solution volume (SA/V) values of 100, 500, 2500 and 10000 m-1, and temperatures of 90 and 150°C were considered. High SA/V and T were especially used to accelerate the corrosion. The leaching medium was distilled water, total durations up to 600 days, and the test were interpreted in terms of solution composition either without or after ultrafiltration. The data reveal that long term dissolution of the soluble elements B, Na and Li is diffusion-controlled for all glasses. SA/V appears to be a meaningful corrosion accelerating parameter. The glass composition determines the sequence and kind of the dissolution processes, but final solution data for the soluble elements are not that different. The {"}final{"} experimental data for B range between 700 and 1050 mgl-1 at 90°C (105 days at 10000 m-1), and between 19000 and 56000 mgl-1 at 150°C (400 days at 10000 m-1).",
keywords = "Corrosion",
author = "{Van Iseghem}, Pierre and Takayuki Amaya and Yasuhiro Suzuki and H. Yamamoto",
note = "Score=10",
year = "1992",
doi = "10.1016/0022-3115(92)90090-8",
language = "English",
volume = "190",
pages = "269--276",
journal = "Journal of Nuclear Materials",
issn = "0022-3115",
publisher = "Elsevier",

}

RIS - Download

TY - JOUR

T1 - The role of Al2O3 in the long-term corrosion stability of nuclear waste glasses

AU - Van Iseghem, Pierre

AU - Amaya, Takayuki

AU - Suzuki, Yasuhiro

AU - Yamamoto, H.

N1 - Score=10

PY - 1992

Y1 - 1992

N2 - The corrosion stability of borosilicate waste glasses has been investigated, as a function of the AlO1.5 (in balance with SiO2) content. The AlO1.5 content ranged from 6.7 to 18.2 mol%. Surface area to solution volume (SA/V) values of 100, 500, 2500 and 10000 m-1, and temperatures of 90 and 150°C were considered. High SA/V and T were especially used to accelerate the corrosion. The leaching medium was distilled water, total durations up to 600 days, and the test were interpreted in terms of solution composition either without or after ultrafiltration. The data reveal that long term dissolution of the soluble elements B, Na and Li is diffusion-controlled for all glasses. SA/V appears to be a meaningful corrosion accelerating parameter. The glass composition determines the sequence and kind of the dissolution processes, but final solution data for the soluble elements are not that different. The "final" experimental data for B range between 700 and 1050 mgl-1 at 90°C (105 days at 10000 m-1), and between 19000 and 56000 mgl-1 at 150°C (400 days at 10000 m-1).

AB - The corrosion stability of borosilicate waste glasses has been investigated, as a function of the AlO1.5 (in balance with SiO2) content. The AlO1.5 content ranged from 6.7 to 18.2 mol%. Surface area to solution volume (SA/V) values of 100, 500, 2500 and 10000 m-1, and temperatures of 90 and 150°C were considered. High SA/V and T were especially used to accelerate the corrosion. The leaching medium was distilled water, total durations up to 600 days, and the test were interpreted in terms of solution composition either without or after ultrafiltration. The data reveal that long term dissolution of the soluble elements B, Na and Li is diffusion-controlled for all glasses. SA/V appears to be a meaningful corrosion accelerating parameter. The glass composition determines the sequence and kind of the dissolution processes, but final solution data for the soluble elements are not that different. The "final" experimental data for B range between 700 and 1050 mgl-1 at 90°C (105 days at 10000 m-1), and between 19000 and 56000 mgl-1 at 150°C (400 days at 10000 m-1).

KW - Corrosion

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/axs_16239

U2 - 10.1016/0022-3115(92)90090-8

DO - 10.1016/0022-3115(92)90090-8

M3 - Article

VL - 190

SP - 269

EP - 276

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

SN - 0022-3115

ER -

ID: 3473082