Selected research topics on nuclear reactor thermal hydraulics

In the presentation some aspects of nuclear reactor thermal hydraulics are discussed. It focusses on accident analyses for loss of coolant accidents (LOCA) and demonstrates the capabilities of system codes. In a second part recent research on the qualification of CFD codes for nuclear reactor safety issues is presented. Special attention is paid to experimental work done at HZDR to obtain CFD-grade experimental data. The TOPFLOW facility is combined with innovative measuring techniques to obtain such data.