The large radial thermal gradient in Sodium-cooled Fast reactors (SFR) leads to mass transport of uranium and plutonium in the fuel pellet. Knowledge of self-diffusion of all these elements in (U,Pu)O2 fuel is therefore of utmost importance for the prediction of its in-pile behaviour. Very few experimental data, however, are available on self-diffusion in this material.
In the inception of...
This work is devoted to the first assessment of the state-of-the-art European fuel performance codes GERMINAL, MACROS and TRANSURANUS against integral and microscopic data from post-irradiation examinations in the fast reactor irradiation experiment SUPERFACT. This activity is performed by a Task Force, including CEA, JRC, ENEA, SCK.CEN and POLIMI, in the framework of the H2020 European...
The fuel creep experiment is currently being prepared within the H2020 INSPYRE project for irradiation in High Flux Reactor in Petten. The goal of this experiment is to produce in-core online measurements of dimensional changes of UO2 and MOX fuel samples under applied axial load.
In this work TRANSURANUS (TU) Fuel Performance Code in combination with Finite Element Analysis (FEA) is used to...
