Two systems were investigated at the Joint Research Centre (JRC)-Karlsruhe for the experimental validation
of the Thermodynamic of Advanced fuels - International Database (TAF-ID). The first system was
representative of ex-vessel corium, consisting of nuclear fuel, fuel cladding, steel, and concrete representative
materials, while the second consisted of (U, Pu)O2 (MOX) with lanthanides (2.5 at.% each of Ce, Gd, La,
and Nd). Experimental observations included laser heating, for measuring liquidus and solidus temperatures;
SEM-EDS, EPMA, and XRD for characterising the fuel microstructure, phases composition, and crystal
structure; and KEMS, for measuring the vapour pressure of species. The obtained results were compared
to thermodynamic calculations using the TAF-ID. Excellent agreement was observed between experimental
and calculated results in the UO2-corium system, particularly of the liquidus and solidus temperatures,
and the composition of phases. Results obtained on the MOX-corium system were not fully conclusive due
to some experimental challenges. They do suggest, however, that some thermodynamic models should be
reviewed, particularly those of U-Zr-O and U-Pu-Zr-O in the hypo-stoichiometric region. Regarding the
MOX-Lanthanides system, evidence of silicon contamination was observed that led to the formation of a
Si-, Pu-, and lanthanide-rich phase in a ratio consistent with M2SiO4.
GEIGER Ernesto;
BENES Ondrej;
VIGIER Jean-Francois;
BOBORIDIS Konstantinos;
ROBBA Davide;
COLLE Jean-Yves;
CREMER Bert;
ERNSTBERGER Markus;
POEML Philipp;
HIMBERT Jerome;
GARDEUR Sebastien;
LAJARGE Patrick;
POPA Karin;
BOSHOVEN Co;
VLAHOVIC Luka;
WISS Thierry;
PIRO Marcus H.;
KONINGS Rudy;
2023-11-27
Publications Office of the European Union
JRC135045
978-92-68-08691-9 (online),
1831-9424 (online),
EUR 31715 EN,
OP KJ-NA-31-715-EN-N (online),
https://publications.jrc.ec.europa.eu/repository/handle/JRC135045,
10.2760/693912 (online),
