Facility Details: VULCANO/VITAE

DataBase Source Term - Focus area 1: Fission product release (including in-vessel, ex-vessel) (1)
Organization / Localization: CEA Cadarache
Country:
Facility Description: to perform experiments with prototypic corium with realistic chemical composition including depleted UO2
Facility Status:
Test Identification: Spreading tests: VE-01, VE-02, VE-03, VE-04, VE-07 VE-U1, VE-U3, VE-U5, VE-U7, VE-U8 URASOL/ VITAE InV
SA-Related Topics / Phenomena: Study of corium transport and spreading on refractory bricks (e.g. zirconia or magnesia), steel or concrete. Also the physico-chemical properties of corium and its influence on long-term behavior. Aerosol (incl. FPs) released from thermal treatment of prototypic fuel debris sample
Measured Parameters: Mass flowrate Temperature Spreading progression and front velocity Chemical composition
Modelling: 3 temperature ranges: RT to 1800°C, 1800-2300°C, 2300-2600°C.
Simulation Code: THEMA CORFLOW LAVA MPS MELTSPREAD
Experimental Research Program: Corium Spreading and Coolability project ECOSTAR project OECD/BSAF benchmark
Link to PIRT: WP-1.5 ST-4
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References: [1] Christophe Journeau et al., «Ex-vessel corium spreading: results from the VULCANO spreading tests», Nuclear Engineering and Design, vol. 223-1, p. 75-102, 2003, https://doi.org/10.1016/S0029-5493(02)00397-7
[2] Christophe Journeau et al., «The VULCANO VE-U7 Corium spreading benchmark», Progress in Nuclear Energy, vol. 48-3, p. 215-234, 2006, https://doi.org/10.1016/j.pnucene.2005.09.009
[3] Christophe Journeau et al., «Chemical composition of aerosols generated by heating prototypic fuel debris samples», Science Talks, vol. 6, p. 100215, 2023, https://doi.org/10.1016/j.sctalk.2023.100215
[4] Yusan Yasumura et al., «Investigation on influence of crust formation on VULCANO VE-U7 corium spreading with MPS method», Annals of Nuclear Energy, vol. 107, p. 119-127, 2017,
https://doi.org/10.1016/j.anucene.2017.04.002
[5] Farmer, Mitch, «Melt spreading code assessment, modifications, and application to the EPR core catcher design», 2009, 10.2172/951260.

Comments: Simulation of fuel debris thermal cutting. Provides information on releases from Lower Head pool
Contributed By: C.Journeau




Implemented as part of the Seaknot EU funded project (HORIZON-EURATOM-2021-NRT-01 under Grant Agreement No. 101060327) - WP2.6 UNIPI (2024-2026)