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Guy G. Loomis, Rex W. Shumway
Nuclear Technology | Volume 63 | Number 1 | October 1983 | Pages 151-163
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33310
Articles are hosted by Taylor and Francis Online.
Flow film boiling heat transfer data from Semiscale Mod-3 gravity feed reflood experiments have been compared to existing film boiling correlations. The existing film boiling correlations were found to be inadequate for calculating Semiscale rod bundle results in the low void fraction region. Therefore, a new correlation for flow film boiling was developed. The new correlation is applicable for boiling water with stainless steel electrically heated vertical rods for a pressure range from 127 to 390 kPa. The new correlation is sensitive to such parameters as the local void fraction, the wall temperature, the bulk vapor temperature, and the total mass flux.