NuFuel-MMSNF 2019 Workshop

Session

Session 7

7

6 Nov 2019, 14:00

WHGA/001 (PSI Auditorium)

41. New insight into the thermodynamic and atom transport properties of (U,Pu)O$_2$ nuclear fuel from atomic scale calculations

Marjorie Bertolus (CEA)

06/11/2019, 14:00

The uranium-plutonium mixed oxide (U,Pu)O$_2$ is currently used as nuclear fuel in pressurized water reactors with a Pu content around 10 wt.%, and is the reference fuel for several Generation IV reactors with a Pu content between 25 and 40 wt.%. A more precise knowledge of the properties of (U,Pu)O$_2$ and its behaviour under irradiation is needed to refine the models used in the fuel...

14. Development of a thermo-kinetic model of cations in the mixed oxide of Uranium & Plutonium

Prantik Chakraborty (Den-Service de la Corrosion et du Comportement des Matériaux dans leur Environnement (SCCME), CEA, Université Paris-Saclay, F-91191, Gif-sur-Yvette, France)

06/11/2019, 14:30

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...

35. Assessment of the current European Fuel Performance Codes against the Fast Reactor irradiation experiment SUPERFACT

Alessio Magni (Politecnico di Milano)

06/11/2019, 14:50

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...

53. Modelling of the H2020 INSPYRE fuel creep experiment in HFR with TRANSURANUS

Alexander Fedorov (Nuclear Research and consultancy Group)

06/11/2019, 15:10

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...