Ex-vessel fuel-coolant interaction experiment in the DISCO facility in the LACOMECO project. Issue 5 (3rd May 2016)

• Record Type: Journal Article
• Authors: Miassoedov, Alexei; Albrecht, Giancarlo; Meyer, Leonhard; Meignen, Renaud
• Is Part Of: Journal of nuclear science and technology. Volume 53:Issue 5(2016)
• Page Start: 639
• Page End: 646
• Publication Date: 2016-05-03
• Subjects: safety -- severe accident -- experiment -- ex-vessel -- corium -- FCI; Nuclear engineering -- Periodicals; Nuclear physics -- Periodicals; Nuclear energy -- Periodicals; 621.4805
• DOI: 10.1080/00223131.2015.1127785
• Languages: English
• ISSNs: 0022-3131

Abstract

Abstract : In the frame of the LACOMECO (large scale experiments on core degradation, melt retention and containment behavior) project of the 7th European Framework Program, a test in the DISCO (dispersion of corium) facility was performed in order to analyze the phenomena which occur during an ex-vessel fuel–coolant interaction (FCI). The test is focused on the premixing phase of the FCI with no trigger used for explosion phase. The objectives of the test were to provide data concerning the dispersion of water and melt out of the pit, characterization of the debris and pressurization of the reactor compartments for scenarios, where the melt is ejected from the reactor pressure vessel (RPV) under pressure. The experiment was performed for a reactor pit geometry close to a French 900 MWe reactor configuration at a scale of 1:10. The corium melt was simulated by a melt of iron–alumina with a temperature of 2400 K. A containment pressure increase of 0.04 MPa was measured, the total pressure reached about 0.24 MPa. No spontaneous steam explosion was observed. About 16% of the initial melt (11.62 kg) remained in the RPV vessel, 60% remained in the cavity mainly as a compact crust. The fraction of the melt transported out of the pit was about 24%.