Abstract
Abstract An extensive experimental program was performed to investigate departure from nucleate boiling (DNB) in electrically heated rod bundles simulating a nuclear power reactor fuel assembly. Effects on DNB due to non-uniform axial heat flux distribution, geometry of spacer grids (with and without mixing vane), length, and axial grid spacing along the rods were investigated. The experimental ranges were pressure: 1490–2400 psia; inlet temperature: 431–627°F; and mass velocity: 1.02–3.95 × 10 6 lb/hr ft 2 . The 284 DNB data points obtained were compared with DNB heat fluxes predicted by the non-uniform heat flux W-3 correlation with a grid factor, based on local conditions calculated by the THINC computer code. This correlation accurately predicted the DNB heat fluxes in axially non-uniformly heated rod bundles, with a standard deviation of 7.4% and a mean deviation of +2.4% from the observed results.
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