TAF-ID: An international thermodynamic database for nuclear fuels applications

نویسندگان

چکیده

Abstract The Thermodynamics of Advanced Fuels – International Database (TAF-ID) was developed using the Calphad method to provide a computational tool perform thermodynamic calculations on nuclear fuel materials under normal and off-normal conditions. Different kinds fuels are considered: oxide, metallic, carbide nitride fuels. Many fission products introduced as well structural (e.g., zirconium, steel, concrete, SiC) absorbers B4C), in order investigate thermochemistry irradiated predict their chemical interaction with surrounding materials. approach develop database models implemented described. Examples for key systems presented. Finally, few examples application severe accidents UO2 fuels, chemistry MOX metallic fuel/cladding show how this can be used. To validate database, compared available experimental data. A good agreement is obtained which gives confidence maturity degree quality TAF-ID database. working version only accessible participants project (Canada, France, Japan, Netherlands, Republic Korea, United Kingdom, USA). public by all NEA countries. current contains Am–Fe, Am–Np, Am-O-Pu, Am–U, Am–Zr, C–O–U-Pu, Cr–U, Np–U, Np–Zr, O–U–Zr, Re–U, Ru–U, Si–U, Ti–U, U-Pu-Zr, U–W systems. It progressively extended our published assessments. Information join website: https://www.oecd-nea.org/science/taf-id/ .

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ژورنال

عنوان ژورنال: Calphad-computer Coupling of Phase Diagrams and Thermochemistry

سال: 2021

ISSN: ['1873-2984', '0364-5916']

DOI: https://doi.org/10.1016/j.calphad.2020.102212