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-- Select Test type--
DataBase Ex-Vessel - Focus area 1: Ex-vessel fuel coolant interaction (EVFCI)
DataBase Ex-Vessel - Focus area 2: Ex-vessel debris cooling, and recriticality (EVDC)
DataBase Ex-Vessel - Focus area 3: Molten corium concrete interaction and corium spreading (MCCIS)
DataBase Ex-Vessel - Focus area 4: Corium properties-(COP)
DataBase In-Vessel - Focus area 1: Mechanical degradation of the reactor core
DataBase In-Vessel - Focus area 2: Melt pool behaviour
DataBase In-Vessel - Focus area 3: Re-flooding of degraded rod bundles
DataBase In-Vessel - Focus area 4: Fission products release
DataBase In-Vessel - Focus area 5: Debris bed quenching
DataBase In-Vessel - Focus area 6: Melt-water interaction
DataBase In-Vessel - Focus area 7: Hydrogen release due to the core oxidation
DataBase In-Vessel - Focus area 8: Reactor Pressure Vessel Integrity
DataBase Source Term - Focus area 1: Fission product release (including in-vessel, ex-vessel)
DataBase Source Term - Focus area 2: Fission product chemistry, transport and remobilization behaviour in RCS
DataBase Source Term - Focus area 3: Fission product chemistry, distribution and remobilization behaviour in containment
DataBase Source Term - Focus area 3: Fission product chemistry, distribution and remobilization behaviour in containment
DataBase Source Term - Focus area 4: Fission product mitigation actions (e.g. FCVS, spray) and containment bypass scenarios
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Albuquerque, NM, USA
Chalk River, Ontario, Canada
China
Czech Republic
Finland
Finland, France
France
Germany
Harrisburng, Pa, USA
Hungary
Idaho, ISA
Idaho Falls, ID, USA
Ispra, Italy
Italy
Japan
Kazakhstan
Korea
Russia
Spain
Sweden
Switzerland
UK
USA
Implemented as part of the
Seaknot EU funded project
(HORIZON-EURATOM-2021-NRT-01 under Grant Agreement No. 101060327) - WP2.6 UNIPI (2024-2026)