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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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Researchers use one-of-a-kind expertise and capabilities to test fuels of tomorrow
At the Idaho National Laboratory Hot Fuel Examination Facility, containment box operator Jake Maupin moves a manipulator arm into position around a pencil-thin nuclear fuel rod. He is preparing for a procedure that he and his colleagues have practiced repeatedly in anticipation of this moment in the hot cell.
Joel Weisman
Nuclear Technology | Volume 99 | Number 1 | July 1992 | Pages 1-21
Critical Review | doi.org/10.13182/NT92-A34699
Articles are hosted by Taylor and Francis Online.
The phenomena governing the critical heat flux (CHF) in flow boiling in ducts and rod bundles vary with the flow pattern. Separate models are needed for dryout in annular flow, wall overheating in plug or slug flow, and formation of a vapor blanket in dispersed flow. The major theories and their current status are described for the annular and dispersed regions. The need for development of a theoretical approach in the plug and slug flow region is indicated. Current phenomenological models are capable of providing satisfactory predictions of rod bundle CHF in both the annular and dispersed flow areas. However, the precision obtained remains below that of empirical correlations.