Thermophysical properties of liquid UO2, ZrO2 and corium by molecular dynamics and predictive models

JOURNAL OF NUCLEAR MATERIALS

卷:491

Article

Kim, Woong Kee¹  Shim, Ji Hoon^1,3  Kaviany, Massoud^1,2 

[1] Pohang Univ Sci & Technol, Div Adv Nucl Engn, Pohang 37673, South Korea

[2] Univ Michigan, Dept Mech Engn, Ann Arbor, MI 48109 USA

[3] Pohang Univ Sci & Technol, Dept Chem, Pohang 37673, South Korea

关键词: Molten (liquid) corium;    Molten (liquid) UO2;    Molten (liquid) ZrO2;    Classical molecular dynamics;    Density;    Specific heat;    Heat of fusion;    Compressibility;    Viscosity;    Surface tension;    Thermal conductivity;   

DOI  :  10.1016/j.jnucmat.2017.04.030

来源: Elsevier

【 摘 要 】

Predicting the fate of accident-melted nuclear fuel-cladding requires the understanding of the thermophysical properties which are lacking or have large scatter due to high-temperature experimental challenges. Using equilibrium classical molecular dynamics (MD), we predict the properties of melted UO2 and ZrO2 and compare them with the available experimental data and the predictive models. The existing interatomic potential models have been developed mainly for the polymorphic solid phases of these oxides, so they cannot be used to predict all the properties accurately. We compare and decipher the distinctions of those MD predictions using the specific property-related autocorrelation decays. The predicted properties are density, specific heat, heat of fusion, compressibility, viscosity, surface tension, and the molecular and electronic thermal conductivities. After the comparisons, we provide readily usable temperature-dependent correlations (including UO2-ZrO2 compounds, i.e. corium melt). (C) 2017 Elsevier B.V. All rights reserved.

【 授权许可】

Free