Japan Atomic Energy Agency
Thermodynamic database for nuclear fuels and
reactor materials

Database overview

This thermodynamic database have been developed to provide the proper phase diagrams and the related thermodynamic data for multi-purposes, including the evaluation of degradation behaviour of fuel assembly. For example, the advanced fuel degradation models are being developed in JAEA within the project of “Advanced Multi-scale Modeling and Experimental Tests on Fuel Degradation in Severe Accident Conditions”, which was supported by Ministry of Economy, Trade and Industry, Japan.

For the evaluation of the fuel degradation progressions in severe accident conditions, the database includes various elements, such as fuel materials, control rod/blade materials and concrete materials; i.e. UO2-ZrO2-Al2O3-CaO-SiO2-FeO and Zr-Fe-Cr-Ni-B-C-O systems. We have been continuing the improvements and integrations on the database.

The contents of our database are nearly at the same level as NUCLEA database, and the all parameters stored in our database were carefully reviewed by our project members.

The database is constructed with the same format as the TAF-ID database developed in a OECD/NEA joint project, and available in Thermo-Calc software.

If you would like to have further information about the database, please contact our webmaster.

Output samples

Phase diagrams Thermodynamic data tables Liquidus·solidus surfaces

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