首页|Development of the Molten Salt Thermal Properties Database - Thermochemical (MSTDB -TC), example applications, and LiCl -RbCl and UF3-UF4 system assessments

Development of the Molten Salt Thermal Properties Database - Thermochemical (MSTDB -TC), example applications, and LiCl -RbCl and UF3-UF4 system assessments

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  • NSTL
  • Elsevier
The Molten Salt Thermal Properties Database - Thermochemical (MSTDB -TC) has been developed to support thermodynamic modeling of fluoride-and chloride-based systems for molten salt reactors (MSRs). Utilizing data from available literature and original work, the current MSTDB -TC Ver. 1.2 contains models for 96 pseudo-binary systems, 37 pseudo-ternary systems, 42 solid solutions, 229 stoichiometric compounds, and 130 gaseous species. This includes 67 reassessed systems and 13 original system models. The reassessment of the LiCl-RbCl pseudo-binary system and the original assessment of the UF3-UF4 pseudo-binary system are included as examples of those effort s and provide improved representations of those systems. The database continues to be expanded, adding systems of relevance to the wide variety of MSR concepts. To illustrate applications for MSTDB -TC, phase equilibria were computed to understand the effect of varying uranium content in the KCl-MgCl2-NaCl -UCl3 system. In an example of how such calculations can support corrosion modeling, the control of redox potential by the UF3:UF4 ratio in the LiF-BeF2-UF3 -UF4 system is demonstrated and used to assess corrosion potential for typical alloy constituents.(C) 2022 Elsevier B.V. All rights reserved.

Thermodynamic modelingCALPHADMolten salt reactor (MSR)Modified quasi-chemical model (MQM)Fluoride salt systemChloride salt systemQUASI-CHEMICAL MODELTHERMODYNAMIC EVALUATIONPHASE-DIAGRAMSOPTIMIZATIONFLUORIDECOORDINATIONBINARYKCLNAEQUILIBRIA

Ard, Johnathon C.、Yingling, Jacob A.、Johnson, Kaitlin E.、Schorne-Pinto, Juliano、Aziziha, Mina、Christian, Matthew S.、McMurray, Jacob W.、Besmann, Theodore M.、Dixon, Clara M.

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Univ South Carolina

Oak Ridge Natl Lab

2022

10.1016/j.jnucmat.2022.153631

Journal of Nuclear Materials

Journal of Nuclear Materials

EISCI
ISSN：0022-3115
年,卷(期)：2022.563
  • 13
  • 94