SADD - Severe accident database directory

DataBase In-Vessel - Focus area 8: Reactor Pressure Vessel Integrity (1)

Facility Name	Test Identification	Measured Parameters	Modelling	Simulation Code	Experimental Research Program	Country
INVECOR	4 tests which a mixture of UO2, ZrO2 and various amounts of metallic Zr pieces heated to simulate corium in different oxidation states	interaction of corium melt (60 kg) with the reactor vessel steel during decay heating (6–9 W/cm3)				Kazakhstan
▼ Show/Hide Additional Details References: [1] Zhdanov, V., Baklanov V., Bottomley, P.D.W., Miassoedov, A., Tromm, T. W., Journeau, Ch., Altstadt, E., Clément, B., Oriolo, F., 2011. Study of processes of coriummelt retention in the reactor pressure vessel (INVECOR), Proc. ICAPP’11, Nice, France. [2] Plevacova, K., Journeau, C., Piluso, P., Zhdanov, V., Baklanov, V., Poirier, J., 2011. Zirconium carbide coating for corium experiments related to water-cooled and sodiumcooled reactors. J. Nucl. Mater. 414, 23–31. Contributed By: F. Gabrielli IP/Copyright Situation: To be Checked

RPV failure