Redox chemistry, solubility and hydrolysis of uranium in dilute to concentrated salt systems

Uranium is the main element present in spent nuclear fuel and accordingly contributes with the largest mass inventory to the nuclear waste. In spite of uranium being a relatively minor contributor to the overall radiological dose of the waste, it is certainly required to have an accurate knowledge on the solution chemistry and solubility phenomena of this key element. Uranium is also a redox-sensitive actinide, and accordingly its chemical behavior is strongly dependent on the redox boundary conditions of the system. Disposal of spent fuel in deep geological formations such as crystalline/granite, clay and rock salt is the option favored by international consensus. Water intrusion is a possible scenario that needs to be accounted for in the context of the long-term Safety Assessment of these repositories. The composition of the pore water contacting the waste will largely vary depending upon host-rock, backfill and other technical barriers, as well as the waste itself. Although a vast number of studies have previously investigated the solution chemistry of uranium, a number of key uncertainties remain. These affect to redox behavior, solid phases controlling solubility and hydrolysis, especially in the alkaline to hyperalkaline pH conditions of relevance in the context of nuclear waste disposal. U(IV) and U(VI) are the most stable oxidation states of uranium controlling its solution chemistry and solubility within the stability field of water and in the absence of strong complexing ligands. The study of this redox couple in the alkaline reducing conditions relevant in certain concepts for waste disposal (e.g. cementitious) is challenged by the further stabilization of U(VI) in the hyperalkaline pH-region, and the high sensitivity of U(IV) towards oxidation in the presence of traces of oxygen. Accordingly, an adequate knowledge of uranium redox chemistry in the aqueous and solid phases under geochemical boundary conditions (pH, pe, ionic strength, etc.) relevant in the context of nuclear waste disposal is important for a correct assessment of the long-term safety. For this reason, the redox chemistry of uranium in the presence of various reducing chemical systems in dilute to concentrated NaCl solutions is investigated in acidic to hyperalkaline pH conditions, and the results summarized in Chapter 3 of this PhD thesis. The kinetics of the reduction of U(VI) to U(IV), as well as the effect of the type and concentration of the reducing system are investigated by systematic measurements of the pHm (with pHm = –log [H+] in molal units), pe and U concentrations until attaining equilibrium conditions. Complete reduction of U(VI) to U(IV) is observed in most of the cases within the boundary conditions (pe + pHm) ≤ 4, although reduction kinetics are strongly impacted by [U(VI)]0, pHm, type and concentration of the reducing system and NaCl concentration. In (oversaturated) alkaline NaCl systems, solubility data and XANES indicate that the reduction proceeds via fast precipitation of Na2U2O7xH2O(cr), which slowly transforms into a UO2(am, hyd) solid phase. In less favourable conditions, the completion of this process required ≈ 635 days. These results also preclude the predominance of the U(IV) anionic hydrolysis species U(OH)5– and U(OH)62– below pHm ≈ 14.5, previously reported in the literature. Experimental data obtained within this PhD thesis indicate that previous observations reported in the literature can be possibly explained by insufficient equilibration time. Furthermore, this study confirms the key role of U(IV) in controlling the solubility and solution chemistry of uranium in reducing, alkaline systems. Very reducing conditions are expected to develop after the closure of underground repositories for nuclear waste disposal due to the anoxic corrosion of steel and iron components. As demonstrated in Chapter 3, U(IV) is expected to control the solubility and aqueous speciation of uranium under these very reducing conditions over a broad range of pH and background electrolyte concentrations. In spite of this, key uncertainties still affect the solution chemistry of U(IV), in particular with regard to the properties of the oxo-hydroxide/s solid phases forming, the aqueous speciation in alkaline to hyperalkaline pH conditions, as well as the formation and stability of U(IV) “intrinsic colloids”. In this context, Chapter 4 of this PhD thesis focuses on the investigation of the solubility and hydrolysis of U(IV) in reducing, dilute to concentrated NaCl, MgCl2 and CaCl2 solutions. A very thorough solid phase characterization including XRD, SEM-EDS, quantitative chemical analysis, EXAFS and TG-DTA confirms that a (nano-)crystalline phase, UO2xH2O(ncr), is responsible for the control of the solubility of U(IV) in the investigated conditions. The systematic investigation of the solubility of this solid phase in dilute to concentrated, acidic to hyperalkaline pHm conditions allows deriving comprehensive chemical, thermodynamic and SIT activity models for the system U4+–Na+–Mg2+–Ca2+–H+–Cl––OH––H2O(l). The investigation of supernatant solutions in solubility experiments without the use of phase separation methods gives also insight on the colloidal fraction in “equilibrium” with UO2xH2O(cr). Although a systematically increased uranium concentration (ca. 2–3 log10-units) is observed with respect to 10 kD ultrafiltered samples, a clear trend to decreasing [U]aq with longer equilibration times is also indicated in solubility experiments within t ≤ 200 days. Hence, the contribution of U(IV) “intrinsic colloids” to the solubility is evident in all salt systems investigated in this work, but the long-term stability of such species remains unclear. Uranium is mostly found as U(VI) under mildly reducing to oxidizing conditions. In the close vicinity of spent nuclear fuel surfaces, radiolysis effects can also promote the formation of U(VI) even in the presence of H2(g). Under alkaline pH conditions and in the absence of complexing ligands (e.g. carbonate, phosphate, silicate), the solubility of U(VI) is expectedly controlled by M–U(VI)–OH uranate solid phases (with M = Na, K, Ca, among others). In contrast to Ca- and Na-uranates, very little is known on the solubility of K–U(VI)–OH phases in spite of the abundance of K+ in many types of groundwaters and, in particular, the key role of this alkali ion in cementitious systems. In this context, Chapter 5 of this PhD is dedicated to the study of U(VI) solubility in alkaline, dilute to concentrated KCl solutions. Comprehensive solubility experiments with systematic variation of pHm and ionic strength, in combination with an extensive solid phase characterization (XRD, SEM–EDS, quantitative chemical analysis, TG-DTA) resulted in thermodynamic and activity models for the system UO22+–K+–Na+–H+–Cl––OH––H2O(l). Sensitivity analysis conducted using this updated thermodynamic model confirms that K- and Na-uranates (K2U2O7x1.5H2O(cr) and Na2U2O7xH2O(cr), respectively) are responsible of controlling the solubility of U(VI) under boundary conditions defined by cementitious systems. The absence of these solid phases in the corresponding thermodynamic databases leads to a very large overestimation (2–6 log10-units), depending upon pHm and alkali concentration) of U concentration in the underlined conditions. This work provides improved fundamental understanding of uranium solution chemistry, including redox processes, solubility phenomena and hydrolysis of both +IV and +VI redox states. Thermodynamic constants derived in the standard state and (SIT) ion interaction coefficients obtained can be implemented in thermodynamic databases and used in geochemical calculations under a variety of boundary conditions. This covers dilute to concentrated salt systems, thus allowing thermodynamic calculations under conditions representative of the different host-rocks foreseen for repositories for nuclear waste disposal, from crystalline and clay to salt-rock

Interaction of Ln(III) and An(III)/IV/V/VI) with borate in dilute to concentrated NaCl, CaCl2 and MgCl2 solutions

Die Wechselwirkung von Ln(III) und An(III,IV,V,VI) mit Borat wurde mit umfassenden Löslichkeitsexperimenten, Festphasencharakterisierung und spektroskopischen Studien in verdünnt bis konzentrierten NaCl-, CaCl2- und MgCl2-Lösungen untersucht

Redox, solubility and sorption chemistry of technetium in dilute to concentrated saline systems (KIT Scientific Report ; 7703)

This PhD work represents a comprehensive investigation of redox processes, solubility and sorption behaviour of technetium in the absence of complexing ligands extending from dilute to concentrated NaCl, MgCl2 and CaCl2 systems. The complete chemical, thermodynamic and activity models derived in this work provide key input for understanding the chemical behaviour of Tc in conditions relevant for nuclear waste disposal

Proceedings of the International Workshop ABC-Salt (II) and HiTAC 2011 (KIT Scientific Reports ; 7625)

In November 2011, the Institute for Nuclear Waste Disposal at the Karlsruhe Institute of Technology hosted two workshops targeting topics of high importance to the safe disposal of nuclear waste, ABC-Salt(II) and HiTAC. The Proceedings comprise main conclusions from the workshops and highlight recent research on actinide and brine chemistry relevant to waste disposal in rock-salt formations and high temperature aqueous chemistry relevant for the disposal of heat producing radioactive waste