Abstract
MYRRHA represents an innovative and unique facility designed to demonstrate the feasibility of the ADS concept at reasonable power levels and to pave the way towards the next generation of nuclear reactors. At the same time, this versatile infrastructure aims to support the ALFRED reactor. In the framework of investigating MYRRHA fuel pin thermo-mechanical behavior during transient conditions, the TRANSURANUS fuel performance code along with ANSYS, were used for thermo-mechanical simulations on three experimental fuel pins containing UO2 pellets and 15-15Ti clad, surrounded by stagnant LBE coolant, irradiated in the ACPR-TRIGA reactor at ICN Pitesti. The results concern both fuel and cladding performance and are compared with the available experimental data.
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