Benchmark Experiment on Critical Heat Flux of PWR Fuel Assembly

Critical heat flux（CHF） under different condition is important to the thermal-hydraulics design and safety analysis. Benchmark experiment is carried out with full length non-uniform power distribution rod bundle using Large Scale Thermal Hydraulics Test Facility（LS-THTF） of NPIC（Nuclear Power Institute of China）. The facility, rod bundle and experiment method are introduced. The CHF data using power of rod bundle are directly compared with the reference measured data from HTRF of Columbia University. In the indirect comparison, the measured CHF data are reduced to compare the Measured to Predicted ratio（M/P） of local heat flux using the sub-channel code combined with CHF correlation. The results show good agreement between CHF data from LS-THTF and HTRF.