Title: Investigations of the melting behaviour of the U-Zr-Fe-O system
Citation: JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY vol. 52 no. 10 p. 1217 - 1225
Publication Year: 2015
JRC N°: JRC95098
ISSN: 0022-3131
URI: http://publications.jrc.ec.europa.eu/repository/handle/JRC95098
DOI: 10.1080/00223131.2015.1023381
Type: Articles in periodicals and books
Abstract: 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.
JRC Directorate:Nuclear Safety and Security

Files in This Item:
There are no files associated with this item.

Items in repository are protected by copyright, with all rights reserved, unless otherwise indicated.