Investigations of the melting behaviour of the U-Zr-Fe-O system

During a severe nuclear accident, the UO2 fuel rods, Zircaloy cladding, guide tubes, absorber and steel structural components inside the reactor pressure vessel overheat and a series of interactions between these elements and the steam atmosphere occur. These produce more heat in addition to the decay heat and result in a liquid corium of oxidic and metallic phases depending on the exact conditions and processes. A major systems resulting from this is the U-Zr-Fe-O system. High temperature data for this system is important in order to be able to model these interactions. ITU has been examining the melting ranges for this system over the whole FeO range by means of a specialized laser flash technique that achieves very high temperatures and avoids crucible contamination. The melted zones were examined for their structure, composition and for estmation of the liquidus and solidus temperatures. The results showed that with FeO contents of over 20 mol% there was a very large melting range that would permit long liquid cooling times and extend the relocation of fuel material within the reactor pressure vessel. Based on these results, the main phase regimes expected under severe accident conditions could be identified.

BOTTOMLEY Paul;  MURRAY FARTHING Mairead;  MANARA Dario;  WISS Thierry;  CREMER Bert;  BOSHOVEN Jacobus;  LAJARGE Patrick;  RONDINELLA Vincenzo; 

2015-12-10

TAYLOR & FRANCIS LTD

JRC95098

0022-3131,   

https://publications.jrc.ec.europa.eu/repository/handle/JRC95098,   

10.1080/00223131.2015.1023381,