Sorption behavior of Sr(II) in granitic rock: the effect of MX-80 bentonite colloids-Reference-Cited by-同舟云学术

Sorption behavior of Sr(II) in granitic rock: the effect of MX-80 bentonite colloids

Published:2023-08-08 Issue:9 Volume:332 Page:3719-3732
ISSN:0236-5731
Container-title:Journal of Radioanalytical and Nuclear Chemistry
language:en
Short-container-title:J Radioanal Nucl Chem

Author:

Pakkanen Noora^ORCID,Puhakka Eini,Siitari-Kauppi Marja,Hölttä Pirkko

Abstract

AbstractMX-80 bentonite colloids’ effect on radionuclide sorption was studied by batch method and transport in flow using a granitic drill core column and Sr(II) as a radionuclide. Batch-type sorption and desorption experiments were conducted to determine Sr(II)’s distribution coefficients on bentonite colloids and metatexitic gneiss. Molecular modeling assessed the radionuclide’s sorption affinity and justified the differences in Sr(II)’s sorption behavior on biotite versus montmorillonite. The distribution coefficients were found to be a hundred times greater for colloids than for granitic rock. Strontium’s breakthrough from the column with bentonite colloids was successful without notable retardation on rock minerals.

Funder

CSC – IT Center for Science

HORIZON EUROPE Framework Programme

Fortum and Neste foundation

University of Helsinki including Helsinki University Central Hospital

Publisher

Springer Science and Business Media LLC

Subject

Health, Toxicology and Mutagenesis,Public Health, Environmental and Occupational Health,Spectroscopy,Pollution,Radiology, Nuclear Medicine and imaging,Nuclear Energy and Engineering,Analytical Chemistry

Link

https://link.springer.com/content/pdf/10.1007/s10967-023-09064-3.pdf

Reference63 articles.

1. Geier J, Bath A, Stephansson O (2012) Comparison of site descriptive models for Olkiluoto, Finland and Forsmark. STUK-TR, Sweden, p 14

2. Hellä P, Pitkänen P, Löfman J, Partamies S, Vuorinen U, Wersin P (2014) Safety case for the disposal of spent nuclear fuel at Olkiluoto: definition of reference and bounding groundwaters, buffer and backfill porewaters. Posiva report 2014-04, Posiva

3. POSIVA (2012) Safety case for the disposal of spent nuclear fuel at Olkiluoto: Description of the disposal system. Posiva report 2012-05

4. POSIVA (2017) Safety case plan for the operating license application. Posiva report 2017-02, p 151

5. Poteri A, Nordman H, Pulkkanen V-M, Smith P (2014) Radionuclide transport in the repository near-field and far-field. Posiva report 2014-02, Posiva