MYRRHA fuel transient tests project at the TRIGA-ACPR Reactor

C. Roth, Brian Boer, M. Mladin, A. Datcu, G. Budriman, C. Truta, Kevin Govers

    Research outputpeer-review


    Transient testing of MYRRHA fuel will be performed at the TRIGA-ACPR Reactor. The goal of the project is to establish the fuel failure threshold next to the development of new testing methodologies and experimental devices for the specific conditions of this Liquid Metal Fast Reactor fuel. The preliminary assessment shows that the energy deposition level required for possible cladding failure due to the Pellet Cladding Mechanical Interaction can be achieved during the pulse. Based on the reactor physics assessment and the test fuel segment preliminary design, the conceptual design of a new irradiation rig has been completed. Additional neutron moderator materials are used to modify the neutron spectrum in order to achieve the required fission power density in the test segments. The design of the test rig and the TRIGA-ACPR pulse characteristics have been engineered in such a way that the power and temperature conditions simulate MYRRHA specific transients.
    Original languageEnglish
    Title of host publicationNuclear 2014
    Place of PublicationPitesti, Romania
    StatePublished - 28 May 2014
    Event2014 - NUCLEAR : The 7th Annual International Conference on Sustainable Development through Nuclear Research and Education - ICN, Pitesti
    Duration: 28 May 201429 May 2014


    Conference2014 - NUCLEAR
    Internet address

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