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A thermodynamic model of the molten salt system (Na,Cs,Mg,Pu,Nd)(Cl,I) has been developed in this work to assess the effect of CsI on the melting and vaporization behavior of the nuclear fuel in molten salt reactors. Investigation using X-ray diffraction (XRD) and differential scanning calorimetry (DSC) of the binary systems NdCl<sub>3</sub>-NdI<sub>3</sub> and MgI<sub>2</sub>-NdI<sub>3</sub>, as simulant systems for the analogous Pu system, is presented for the first time. Both systems were found to be binary eutectic systems, with solid solutions NdCl<sub>3-3<i>x</i></sub>I<sub>3<i>x</i></sub> (hexagonal in space group <i>P</i>6<sub>3</sub>/<i>m</i>) and NdCl<sub>3<i>y</i></sub>I<sub>3-3<i>y</i></sub> (orthorhombic in space group <i>Cmcm</i>) in the NdCl<sub>3</sub>-NdI<sub>3</sub> system, and Mg<sub>1-<i>x</i></sub>Nd<sub><i>x</i></sub>I<sub>2+<i>x</i></sub> (hexagonal in space group P 3 m1) in the MgI<sub>2</sub>-NdI<sub>3</sub> system. Additionally, the system CsI-MgI<sub>2</sub> was scrutinized using DSC, confirming the available experimental data in the literature. Furthermore, the investigation of the reciprocal diagonals in the systems (Na,Nd)(Cl,I), (Cs,Mg)(Cl,I), (Mg,Nd)(Cl,I), and (Cs,Nd)(Cl,I) is presented, allowing the characterization of the quaternary behavior of these salts. Based on the experimental data obtained in this work, a CALPHAD model is presented using the quasi-chemical formalism in the quadruplet approximation for the liquid solution. With the aim of modeling the complete (Na,Cs,Mg,Pu)(Cl,I) system, the binary systems NaCl-CsCl, CsCl-MgCl<sub>2</sub>, CsCl-NdCl<sub>3</sub>, NaI-CsI, and CsI-NdI<sub>3</sub> were reassessed based on data from the literature. Furthermore, a CALPHAD model of the PuCl<sub>3</sub> and PuI<sub>3</sub> systems is also presented using Nd as a simulant for Pu in molten halide salts. With the developed thermodynamic models, calculations were finally performed to assess the fission product retention of Cs and I in a molten chloride environment. As opposed to their behavior in molten fluorides, the fission products are well retained in the fuel matrix up to concentrations of at least 5 mol%.
Published in: The Journal of Physical Chemistry B
Volume 130, Issue 12, pp. 3507-3530