International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17)

Modeling of Phenix End-of-Life control rod withdrawal tests with the Serpent-DYN3D code system

28 Jun 2017, 17:50

1h 10m

Yekaterinburg

POSTER Track 6. Test Reactors, Experiments and Modeling and Simulations Poster Session 2

Speaker

Dr Emil Fridman (Helmholtz-Zentrum Dresden-Rossendorf)

Description

The nodal diffusion code DYN3D is under extension for Sodium cooled Fast Reactor (SFR) applications. As a part of the extension a new model for axial thermal expansion of fuel rods was developed. The model provides a flexible way of handling the axial fuel rod expansion that is each sub-assembly and node can be treated independently. In the current paper the new model will be described in details. The performance of the model will be assessed with the help of the benchmark on the control rod withdrawal tests performed during the PHÉNIX end-of-life experiments. The DYN3D results will be tested against the experimental data as well as against the numerical results provided by other participants to the benchmark.

Country/Int. Organization

Germany

Presentation materials

Paper

Paper_IAEA-CN-245-18-modeling_of_Phenix_EN_review.pdf