Organization / Localization: NNC RK
Country: Kazakhstan
Facility Description: Facility Status: Test Identification: 4 tests which a mixture of UO2, ZrO2 and various amounts of metallic Zr pieces heated to simulate corium in different oxidation states
SA-Related Topics / Phenomena: RPV failureMeasured Parameters: interaction of corium melt (60 kg) with the reactor vessel steel during decay heating (6–9 W/cm3)
Modelling: Simulation Code: Experimental Research Program: Link to PIRT: 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