An ab initio molecular dynamics investigation of the thermophysical properties of molten NaCl-MgCl2
- North Carolina State Univ., Raleigh, NC (United States)
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- North Carolina State Univ., Raleigh, NC (United States); Idaho National Lab. (INL), Idaho Falls, ID (United States)
Molten salts have many applications in the nuclear and solar energy industries for thermal storage and heat transfer applications. However, there is a knowledge gap in molten salt thermophysical properties which hinders the technical readiness level of molten salt applications, especially in the nuclear industry. A common method of investigating new materials is through ab initio Molecular Dynamics (AIMD) simulations which is an effective tool to investigate structural and thermophysical properties at realistic temperatures. NaCl-MgCl2 is an inexpensive salt that is a good candidate for use as a heat transfer medium in solar power applications or in the secondary loop of a nuclear reactor. In this article, the thermophysical properties of NaCl-MgCl2 are computed via AIMD calculations to supplement the limited experimental studies in the literature. Here a wide range of compositions and temperatures for the pseudo-binary NaCl-MgCl2 were used to calculate the density, heat capacity, compressibility, enthalpy of mixing, and volumetric thermal expansion coefficient. AIMD is shown to accurately model the densities of molten NaCl-MgCl2 as there is good agreement with the available literature. This work observed a transition to a monotonic increase of the density with respect to MgCl2 composition occurring above 1100 K. The heat capacity values increase uniformly with respect to concentration of MgCl2 at a rate of 2.85 J/mol-K per 10 mol% of MgCl2. Select thermophysical properties are fit to a Redlich-Kister expansion for utilization in multiphysics simulations.
- Research Organization:
- Idaho National Laboratory (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE); USDOE Laboratory Directed Research and Development (LDRD) Program
- Grant/Contract Number:
- AC07-05ID14517
- OSTI ID:
- 1903510
- Alternate ID(s):
- OSTI ID: 1962108
- Report Number(s):
- INL/JOU-22-66001-Rev001
- Journal Information:
- Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 570; ISSN 0022-3115
- Publisher:
- ElsevierCopyright Statement
- Country of Publication:
- United States
- Language:
- English
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