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.
|Title of host publication
|Place of Publication
|Published - 28 May 2014
|2014 - NUCLEAR : The 7th Annual International Conference on Sustainable Development through Nuclear Research and Education - ICN, Pitesti
Duration: 28 May 2014 → 29 May 2014
|2014 - NUCLEAR
|2014-05-28 → 2014-05-29