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Storage of Thermal REactor Safety Analysis data

    The KROTOS test facility is a relatively small scale experimental installation dedicated to the study of:

    • (a) molten fuel-coolant pre-mixing either with prototypic reactor melts or simulants such as alumina up to 5 kg;
    • (b) progression and energetics of spontaneous and triggered fuel-coolant interactions (vapor explosions).

    The aim of the DEFOR (Debris Bed Formation) program is clarification of the phenomena that govern formation of the debris bed in different scenarios of corium melt release into a deep water pool and quantification of the debris bed properties related to coolability.

  • LOBI

    (LWR OFF-NORMAL BEHAVIOUR INVESTIGATION) A Reactor Thermal-Hydraulic Safety Research Programme carried out by the Commission of the European Communities at the Ispra Site of the Joint Research Centre.

  • FARO

    FARO (Furnace And Release Oven) experimental facility began the experiments of the LWR-MFCI phenomena in 1990 in collaboration with several reactor safety research organizations from European Union member countries and with the participation of the United States Nuclear Regulatory Commission.

  • RECI

    The aim of the RECI (RECombiner & Iodine) program was to quantify the iodide → iodine conversion in realistic conditions of recombiner operation, albeit under the following constraints: the experiments were to be performed with non-radioactive substances, and without hydrogen. The comprehensive tests grid allowed to investigate into the decomposition of cesium and cadmium iodides under thermal-hydraulics conditions that mimics the recombiner operation, despite the technical limitations of the RECI test bench.

  • ECO

    In case of a steam explosion, e.g. as a consequence of a severe reactor accident, part of the thermal energy of the melt is transferred into mechanical energy. At Forschungszentrum Karlsruhe, the ECO experiments are being directed to measure the conversion factor under well-defined conditions. The programme was launched in 2000. Alumina from a thermite reaction is used as a simulating material instead of corium. Dimensions of the test facility as well as major test conditions, e.g. temperature and release mode of the melt, water inventory and test procedure, are based on the former PREMIX experiments (from 1994 to 1999).

  • CHIP

    The CHIP programme aims to reduce the level of uncertainty on radioactive iodine releases during a core meltdown accident in a nuclear reactor. The programme results will also be used to better define the means and measures to be implemented in order to limit such releases.

  • Becarre

    Boron carbide rod degradation test and associated releases.

    The experimental programme becarre (2001-2010) belongs to the international “source term” programme. The becarre programme Objectives involve better understanding the degradation phenomena occurring in boron carbide (B4c) control rods during a core meltdown accident and determining the laws governing steam oxidation of B4c pellets and relocated mixtures. These laws will be used to both quantify the gases produced during oxidation, and estimate their potential effect upon iodine releases into the environment. The programme results will help improve the icare 2 code which is being developed by irsn.


    The TOSQAN experimental vessel is a large stainless steel cylindrical enclosure (volume 7m3, height 4m, internal diameter 1.5m) with double walls. A coolant circulates in between the walls to regulate the wall temperature from 60 °C to 160 °C. Non radioactive aerosols, steam and non explosive gases can be injected at different controlled flow rates via diverse injection pipes located at different locations of the enclosure. Different instrumentation is used, namely PIV (particle image velocimetry), LDV (laser doppler velocimetry), rainbow refractometry, out of focus imaging and SRD (spontaneous Raman diffusion) spectrometry.


    The VULCANO facility is mainly composed of a furnace and a test section, which is thoroughly instrumented. In the experiments with prototypic material the furnace has the following characteristics:

    • Capability to melt oxidic mixtures of various compositions (UO2, ZrO2, SiO2, FeOx) with the possible addition of metals.
    • Liquidus temperature of the load between 1700 and 2900 °C.
    • Capacity to melt & pour 100 kg. •Continuous low pouring rates (0.1–1 l/s).

    The objectives of the FOREVER (Failure Of REactor VEssel Retention) tests are to obtain multiaxial creep deformation and vessel failure data for the scaled reactor vessel geometry under prototypical thermal and pressure loading conditions during hypothetical severe accidents.


    Determination of the vaporization rate according to the composition and the thermodynamic conditions of the corium (with FP simulants) was the aim of the COLIMA (COrium LIquid and MAterials) experiments. The facility provided representative conditions of the aerosols suspended inside the containment of PWRs under a severe accident.

Storage of Thermal REactor Safety Analysis Data

STRESA was developed by JRC-Ispra in the year 2000 with the main objective to disseminate documents and experimental data from large in-house JRC scientific projects, and has been extensively used in order to provide a secure repository of experimental data.

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At present time the JRC is engaged in the management of this new version of the STRESA tool to secure the European Union storage for severe accident experimental data and calculations.

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Only registered users may access and make use of the features available in this new version of STRESA. If you are already registered, just login using your ECAS credentials and start using the information system.

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