• MOZART

    The Mozart analytical test program, conducted from 2005 to 2007, was dedicated to the study of oxidation in air of nuclear fuel cladding.

  • QUEOS

    The QUEOS facility serves to study premixing phenomena with solid spheres, i.e. without the danger of a steam explosion and the complication of melt fragmentation.

  • TOSQAN

    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.

  • 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.

  • FOREVER

    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.

  • PAKS

    The OECD-IAEA Paks Fuel Project aimed to support the understanding of fuel behaviour in accident conditions on the basis of analyses of the Paks-2 event. Numerical simulation of the most relevant aspects of the event and comparison of the calculation results with the available information was carried out between 2006 and 2007.

  • HORIZON

    The test section of the facility consists of a scaled-down model of VVER-440 steam generator, which has a bundle of 38 tubes with inlet and outlet chambers (hot and cold chamber, respectively), and a secondary side with the steam outlet line but without droplet separators and steam dryers.

  • KAJET

    The experimental programme named KAJET is being performed to investigate features of a pressurized melt jet and the interaction with substratum material. Compact melt jets, rather than a spray-type melt release, are simulated using iron and aluminium oxide instead of corium. The melt is generated by a thermite reaction.

  • REKO

    The REKO-3 test facility allows the investigation of catalyst samples inside a vertical flow channel under well defined conditions comprising gas mixture, flow rate and inlet temperature.

  • PRELUDE

    This facility comprises a water supply pipe, a quartz test section (110, 180 or 290 mm diameter) in which the debris bed is placed, together with its instrumentation, and a steam relief pipe. It is used to conduct refl ooding tests by means of injecting water onto a bed of metal particles heated by induction.

  • 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.

  • PEARL

    Launched in 2007, the "Debris bed reflooding" (ex-PEARL) experimental research program aims to better understand the behaviour of steam and water flow in a porous medium composed of solid particles at very high temperature under conditions representative of a core melt accident (or severe accident).

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About us

At present time the Nuclear Reactor Safety Assessment Unit (NRSA) of the JRC-Petten 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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Use of STRESA

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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