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Solubility, redox behavior and sorption of Sn(II) and Sn(IV) in cement systems

Huber, Nils ORCID iD icon; Gaona, Xavier ORCID iD icon 1; Dardenne, Kathy ORCID iD icon 1; Altmaier, Marcus ORCID iD icon 1; Geckeis, Horst 1
1 Institut für Nukleare Entsorgung (INE), Karlsruher Institut für Technologie (KIT)

Abstract (englisch):

$^{126}$Sn is a long-lived fission product (t1/2 = 1.1∙106 a) produced in low yield (~ 0.065%) in nuclear reactors. A small inventory of this nuclide is accordingly present in high level radioactive waste (HLW). In addition to 126Sn, the shorter-lived isotopes 119mSn (t1/2 = 0.802 a), 121mSn (t1/2 = 55 a) and 125Sn (t1/2 = 0.0264 a) are also expected in low and intermediate level radioactive waste (L/ILW). Cementitious materials are ubiquitous in underground and near-surface repositories for L/ILW. Hydrated cement is an heterogeneous material mainly consisting of calcium silicate hydrated (C-S-H) phases, portlandite (Ca(OH)2) and calcium aluminate-type phases (AFt, AFm). C-S-H phases have been described as main sink of cationic radionuclides and metal ions [1]. Although tin is primarily expected in the +IV oxidation state, uncertainties on the fG°(Sn4+) and the implications on the E°(Sn4+/Sn2+) are currently motive of debate [2].
Undersaturation solubility experiments with Sn(II) and Sn(IV) were performed within 9 ≤ pHm ≤ 12.8 and 0.1 M ≤ I ≤ 3.5 M in NaCl-NaOH and CaCl2-Ca(OH)2 systems. Batch sorption experiments were conducted with a combination of 112Sn (stable) and 113Sn (t1/2 = 115.09 d) isotopes under Ar atmosphere at T = (22 ± 2) °C. ... mehr


Volltext §
DOI: 10.5445/IR/1000188174
Veröffentlicht am 16.12.2025
Zugehörige Institution(en) am KIT Institut für Nukleare Entsorgung (INE)
Publikationstyp Vortrag
Publikationsdatum 06.11.2024
Sprache Englisch
Identifikator KITopen-ID: 1000188174
HGF-Programm 32.11.01 (POF IV, LK 01) Nuclear Waste Disposal
Veranstaltung Jahrestagung der Fachgruppe Nuklearchemie (2024), Karlsruhe, Deutschland, 05.11.2024 – 07.11.2024
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