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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, length, and axial grid spacing along the rods were investigated. 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.