Low-pressure transient flow film boiling in vertically oriented rod bundles

Journal Article · Sat Oct 01 04:00:00 EDT 1983 · Nucl. Technol.; (United States)

OSTI ID:6925606

Loomis, G G; Shumway, R W

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.

• Research Organization: EG and G Idaho, Inc., P.O. Box 1625, Idaho Falls, Idaho 83415
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 6925606
• Journal Information: Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 63:1; ISSN NUTYB
• Country of Publication: United States
• Language: English

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