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AbstractAbstract
[en] A transient boiling experiment has been run in such a way that one can acquire data in forced convection film, transition, and nucleate boiling regions for a specified pressure, quality, and mass flux. Transient boiling experiments were conducted at the Nuclear Energy Division of the General Electric Company for water in a 0.492 in. ID inconel X-750 tube at mass fluxes of 50,000, 100,000, and 250,000 lbm/hr-ft2, quality range of from 30 to 100 percent and a pressure of 1000 psia. The reduced boiling curves for these data indicated temperature differences at burnout on the order of from 100 to 2000F and temperature differences at the minimum ranging from 700 to 11000F. These results (higher than in other experiments) are felt to be caused by scale deposit, axial conduction, and roughnesses on the test surface. Physical evidence indicates that the test surface became coated with an appreciable scale deposit when subjected to the initial temperatures in excess of 15000F in a steam atmosphere. It has been found (reference [1]1) that BWR fuel will normally have scale deposit on the heat transfer surface and thus the qualitative effects of scale deposits in this report are expected to apply in BWR Loss-of-Coolant accident evaluation. An empirical correlation was developed for the data for minimum film boiling temperature differences. The correlation was based on Berenson's minimum pool film boiling temperature difference correlation in order to provide a technique for extrapolating to different pressures. (U.S.)
Original Title
BWR
Primary Subject
Secondary Subject
Record Type
Journal Article
Journal
Journal of Heat Transfer; v. 97(2); p. 166-172
Country of publication
ACCIDENTS, ALLOYS, BOILING, CHROMIUM ALLOYS, CONVECTION, ENERGY TRANSFER, HEAT TRANSFER, HEATING, HYDROGEN COMPOUNDS, INCONEL ALLOYS, INFORMATION, IRON ALLOYS, NICKEL ALLOYS, NICKEL BASE ALLOYS, OXYGEN COMPOUNDS, PHASE TRANSFORMATIONS, REACTOR ACCIDENTS, REACTORS, TITANIUM ALLOYS, TRANSITION ELEMENT ALLOYS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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