Attempt to model laboratory-scale diffusion and retardation data

Pirkko Hölttä (Corresponding Author), Marja Siitari-Kauppi, M Hakanen, Vesa Tukiainen

Research output: Contribution to journalArticleScientificpeer-review

14 Citations (Scopus)

Abstract

Different approaches for measuring the interaction between radionuclides and rock matrix are needed to test the compatibility of experimental retardation parameters and transport models used in assessing the safety of the underground repositories for the spent nuclear fuel. In this work, the retardation of sodium, calcium and strontium was studied on mica gneiss, unaltered, moderately altered and strongly altered tonalite using dynamic fracture column method. In-diffusion of calcium into rock cubes was determined to predict retardation in columns. In-diffusion of calcium into moderately and strongly altered tonalite was interpreted using a numerical code FTRANS. The code was able to interprete in-diffusion of weakly sorbing calcium into the saturated porous matrix. Elution curves of calcium for the moderately and strongly altered tonalite fracture columns were explained adequately using FTRANS code and parameters obtained from in-diffusion calculations. In this paper, mass distribution ratio values of sodium, calcium and strontium for intact rock are compared to values, previously obtained for crushed rock from batch and crushed rock column experiments. Kd values obtained from fracture column experiments were one order of magnitude lower than Kd values from batch experiments.
Original languageEnglish
Pages (from-to)139-148
Number of pages10
JournalJournal of Contaminant Hydrology
Volume47
Issue number2-4
DOIs
Publication statusPublished - 2001
MoE publication typeA1 Journal article-refereed
Event7th International Conference on Chemistry and Migration Behaviour of Actinides and Fission Products in the Geosphere - Lake Tahoe, United States
Duration: 26 Sep 19991 Oct 1999

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calcium
Calcium
Rocks
tonalite
Strontium
rock
strontium
Sodium
sodium
matrix
experiment
Experiments
Spent fuels
Nuclear fuels
repository
Radioisotopes
mica
gneiss
laboratory
radionuclide

Cite this

Hölttä, Pirkko ; Siitari-Kauppi, Marja ; Hakanen, M ; Tukiainen, Vesa. / Attempt to model laboratory-scale diffusion and retardation data. In: Journal of Contaminant Hydrology. 2001 ; Vol. 47, No. 2-4. pp. 139-148.
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Hölttä, P, Siitari-Kauppi, M, Hakanen, M & Tukiainen, V 2001, 'Attempt to model laboratory-scale diffusion and retardation data', Journal of Contaminant Hydrology, vol. 47, no. 2-4, pp. 139-148. https://doi.org/10.1016/S0169-7722(00)00144-3

Attempt to model laboratory-scale diffusion and retardation data. / Hölttä, Pirkko (Corresponding Author); Siitari-Kauppi, Marja; Hakanen, M; Tukiainen, Vesa.

In: Journal of Contaminant Hydrology, Vol. 47, No. 2-4, 2001, p. 139-148.

Research output: Contribution to journalArticleScientificpeer-review

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T1 - Attempt to model laboratory-scale diffusion and retardation data

AU - Hölttä, Pirkko

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AU - Hakanen, M

AU - Tukiainen, Vesa

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AB - Different approaches for measuring the interaction between radionuclides and rock matrix are needed to test the compatibility of experimental retardation parameters and transport models used in assessing the safety of the underground repositories for the spent nuclear fuel. In this work, the retardation of sodium, calcium and strontium was studied on mica gneiss, unaltered, moderately altered and strongly altered tonalite using dynamic fracture column method. In-diffusion of calcium into rock cubes was determined to predict retardation in columns. In-diffusion of calcium into moderately and strongly altered tonalite was interpreted using a numerical code FTRANS. The code was able to interprete in-diffusion of weakly sorbing calcium into the saturated porous matrix. Elution curves of calcium for the moderately and strongly altered tonalite fracture columns were explained adequately using FTRANS code and parameters obtained from in-diffusion calculations. In this paper, mass distribution ratio values of sodium, calcium and strontium for intact rock are compared to values, previously obtained for crushed rock from batch and crushed rock column experiments. Kd values obtained from fracture column experiments were one order of magnitude lower than Kd values from batch experiments.

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