Advanced Course in Heat Transfer in Nuclear Reactor Safety
DOI: 10.1615/ICHMT.1982.AdvCourHeatTransfNucReactSaf
ISBN Print: 978-0-89116-223-0
3.2 Experimental Results of Critical Heat Flux Measurements in 25-Rod Bundles with Different Types of Grid Spacers
pages 499-510
DOI: 10.1615/ICHMT.1982.AdvCourHeatTransfNucReactSaf.280
摘要
Identical test sections are used to check if it is reasonable to employ model fluids for critical heat flux (CHF) investigations in complex rod bundle geometries. The steady state measurements in freon 12 are extended to mass flow and power transient conditions. It is found that for both fluids the influence of spacer design on CHF is considerable and it depends on steam quality.
The mass flow transients have a considerable positive influence on CHF for relative mass flow change rates higher than 10 %/s. The CHF relative values at mass flow or power transients show similar trends in freon and water.