INTERACTION BETWEEN MOLTEN CORIUM UO2+x-ZrO2-FeOy AND VVER VESSEL STEEL
2010 (English)In: Nuclear Technology, ISSN 0029-5450, Vol. 170, no 1, 210-218 p.Article in journal (Refereed) Published
In case of in-vessel corium retention during a severe accident in a light water reactor, weakening of the vessel wall and deterioration of the vessel steel properties can be caused both by the melting of the steel and by its physicochemical interaction with corium. The interaction behavior has been studied in medium-scale experiments with prototypic corium. The experiments yielded data for the steel corrosion rate during interaction with UO2+x-ZrO2-FeOy melt in air and steam at different steel surface temperatures and heat fluxes from the corium to the steel. It has been observed that the corrosion rates in air and steam atmosphere are almost the same. Further, if the temperature at the interface increases beyond a certain level, corrosion intensifies. This is explained by the formation of liquid phases in the interaction zone. The available experimental data have been used to develop a correlation for the corrosion rate as afunction of temperature and heat flux.
Place, publisher, year, edition, pages
American Nuclear Society, 2010. Vol. 170, no 1, 210-218 p.
Zirconium oxide, Uranium dioxide, Heat flux, Meltdown, Corrosion, Nuclear reactor, Light water reactor, Accident, Pressurized water reactor
IdentifiersURN: urn:nbn:se:kth:diva-53474OAI: oai:DiVA.org:kth-53474DiVA: diva2:470129
QC 201201102011-12-282011-12-282012-01-21Bibliographically approved