CFD Simulations of Selected Steady-State and Transient Experiments in the PLANDTL Test Facility

7th European Thermal-Sciences Conference

Gurgacz, S.^1 ; Bieder, U.^2 ; Gorsse, Y.^2 ; Swirski, K.^1

Institute of Heat Engineering, Warsaw University of Technology, 21/25 Nowowiejska Street, Warsaw

00-665, Poland^1

Commissariat A l'Énergie Atomique et Aux Énergies Alternatives, Gif-sur-Yvette, Cedex

91191, France^2

关键词: Atomic Energy Agency;    Fast neutron reactors;    Natural convection flow;    PLANDTL;    Sodium fast reactors;    Steady state and transients;    SUPERCAVNA;    TrioCFD;   

Others  :  https://iopscience.iop.org/article/10.1088/1742-6596/745/3/032042/pdf
DOI  :  10.1088/1742-6596/745/3/032042

来源: IOP

【 摘 要 】

In Sodium Cooled Fast Neutron Reactors natural convection flow and thermal stratification in the upper plenum may occur under emergency shutdown conditions. Thermal stratification phenomena have been examined experimentally in the PLANDTL facility of the Japan Atomic Energy Agency. This paper presents the results of numerical simulations of selected steady-state and transient experiments in the PLANDTL facility, using TrioCFD/MC2 code developed at CEA. CFD approach for the flow in large volumes and a sub-channel approach for the flow in the core region are used. Calculated results have been validated against experimental values. Validation of the upper plenum modelling has been also made based on CEA Sodium mixed convection experiments.