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Solubility, Speciation and Thermodynamics of PuCO3OH(cr) in Carbonate Containing Solutions

Müller, Philipp 1; David, Fellhauer 1; Dieter, Schild 1; Marcus, Altmaier 1; Xavier, Gaona 1; Horst, Geckeis 1
1 Institut für Nukleare Entsorgung (INE), Karlsruher Institut für Technologie (KIT)

Abstract (englisch):

Emplacement in deep geological repositories is the internationally favored option for the disposal of spent nuclear fuel. With respect to the long-term safety of disposal facilities, the potential release of radionuclide due to the interaction with aqueous solutions is analyzed. Important processes that influence the mobility of radionuclides are solubility equilibria, complexation with inorganic and organic ligands, interaction with mineral phases, etc. The quantification and modeling of the individual processes as a function of various solution parameters such as pHm, ionic strength or redox potentials are based on chemical and thermodynamic models and related databases. Plutonium (Pu) is the main transuranic element in spent nuclear fuel and contributes significantly to its radiotoxicity. Under the reducing conditions of a deep geological repository, the +III and +IV oxidation states of plutonium are predominant. In absence of other complexing ligands than OH-, the solubility behavior of Pu is often controlled by hydrolysis reactions. However, a significant influence of dissolved carbonate on speciation and solubility of Pu is expected due to its known strong interaction with actinides. ... mehr


Zugehörige Institution(en) am KIT Institut für Nukleare Entsorgung (INE)
Publikationstyp Vortrag
Publikationsdatum 12.09.2024
Sprache Englisch
Identifikator KITopen-ID: 1000189036
HGF-Programm 32.11.01 (POF IV, LK 01) Nuclear Waste Disposal
Veranstaltung Plutonium Futures - The Science (2024), Charleston, SC, USA, 08.09.2024 – 12.09.2024
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