European Project "Supercritical Water Reactor - Fuel Qualification Test" (SCWR-FQT): Overview, Results, Lessons Learnt and Future Outlook

Mariana Ruzickova, Ales Vojacek, Thomas Schulenberg, Dirk Visser, Radek Novotny, Attila Kiss, Csaba Maraczy, Aki Toivonen

    Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientific


    The Supercritical Water Reactor (SCWR) is one of the six reactor concepts being investigated under the framework of the Generation IV International Forum (GIF). One of the major challenges in the development of a SCWR is to develop materials for the fuel and core structures that will be sufficiently corrosion-resistant to withstand supercritical water conditions, as well as to gain thermal-hydraulic experimental data that could be used for further improvement of heat transfer predictions in the supercritical region by numerical codes. Previously, core, reactor and plant design concept of the European High Performance Light Water Reactor (HPLWR) have been worked out in substantial detail. As the next step, it has been proposed to carry out a fuel qualification test of a small scale fuel assembly in a research reactor under typical prototype conditions. Design and licensing of an experimental facility for the fuel qualification test, including the small scale fuel assembly, the required coolant loop with supercritical water and safety and auxiliary systems, was the scope of the recently concluded project "Supercritical Water Reactor - Fuel Qualification Test" (SCWR-FQT) described here. This project was a collaborative project co-funded by the European Commission, which took advantage of a Chinese - European collaboration, in which China offered an electrically heated out-of-pile loop for testing of fuel bundles. The design of the facility, and especially of the test section with the fuel assembly, as well as the most important results of steady-state and safety analyses are presented. Material test results of the stainless steels considered for the fuel cladding are briefly summarized. Finally, important outcomes and lessons learnt in the "Education & Training" and "Management" work packages are presented.
    Original languageEnglish
    Title of host publication Proceedings of the 7th International Symposium on Supercritical Water-Cooled Reactors (ISSCWR 2015)
    PublisherVTT Technical Research Centre of Finland
    Number of pages17
    ISBN (Electronic)978-951-38-8289-1
    ISBN (Print)978-951-38-8290-7
    Publication statusPublished - 2015
    MoE publication typeB3 Non-refereed article in conference proceedings
    Event7th International Symposium on Supercritical Water-Cooled Reactors, ISSCWR-7 - Helsinki, Finland
    Duration: 15 Mar 201518 Mar 2015

    Publication series

    SeriesVTT Technology


    Conference7th International Symposium on Supercritical Water-Cooled Reactors, ISSCWR-7
    Abbreviated titleISSCWR-7


    • SCWR
    • Reactor core
    • neutronics
    • fuel designs
    • materials
    • water chemistry
    • corrosion
    • thermal-hydraulics
    • safety analysis
    • balance of plant


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