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  • OECD Halden Reactor Project

    OECD Halden Reactor Project, Fuel and Material Behaviour Section: over 130 scientific, official and industrial organisations from 19 countries participate in the OECD’s Halden Reactor Project (HRP).

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  • MSWI

    MSWI, Melt-Structure-Water Interactions during Severe Accidents in LWRs.

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  • MELCOR

    MELCOR, Review and Ongoing Development of the MELCOR Computer Code for the Analysis of Severe Accidents in Light Water Reactors: the MELCOR computer programme is used to simulate severe accidents in light water reactors.

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  • OECD SCIP

    OECD SCIP, Studsvik Cladding Integrity Project: the cladding tubes of the fuel assemblies surround the nuclear fuel, which is present in the form of tablets (pellets); these tubes form the primary barrier against the release of radioactive fission products.

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  • STARS V

    STARS V, Safety Research in Relation to Transient Analysis for the Reactors in Switzerland: the remit for the STARS project, which has been in progress since 1988, is to update and continue the development of methods and computer programmes used to carry out deterministic safety analyses.

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  • Reactor Safety

    The focus in the area of reactor safety is on materials research for the monitoring of ageing, as well as research on incidents and accidents in order to continue developing safety analyses. In addition, ENSI participates in a series of international database projects, enabling it to obtain information about the causes, frequency and progressions of…

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  • Regulatory research

    In the area of regulatory research, ENSI awards and coordinates projects designed to identify and develop scientific know-how of relevance to the regulatory process. The research focuses on issues of regulatory concern. ENSI supports national and international research in the areas “reactor safety”, “radiological protection”, “transport and waste management” and “human influence, organisation and safety…

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  • Allgemein

    KORA-II

    KORA: Corrosion Crack Growth in Austenitic Structural Materials. KORA deals with ageing processes that affect steel components in the primary circuit in nuclear power plants, focusing specifically on two processes: stress corrosion cracking and corrosion fatigue. Stress corrosion cracking can cause long and thin branched fissures which cannot be detected with the naked eye.

    Long-term Operation of Nuclear Power Plants, Research
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