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Effect of pressure on critical heat flux for water in an internally heated annulus
- 1. Research Reactor Institute, Kyoto University, Kumatori-cho, Sennan-gun, Osaka (Japan)
Description
It was pointed out earlier that existing CHF correlations based upon data for annuli at high pressures did not reproduce CHF very well at the atmospheric pressure. It appears to be necessary to investigate CHF at intermediate pressures to interpret the apparent discrepancy between CHFs at high and low pressures. In view of this an experiment was performed to obtain more information on CHF at intermediate pressures and the effect of pressure was discussed in the present study. It was revealed from this study that the effect of pressure on the CHF in the range from 0.1 to 1 MPa could be explained by the annular flow boundary and the critical quality. (author)
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Additional details
Publishing Information
- Imprint Title
- Proceedings of the fourth international topical meeting on nuclear thermal hydraulics, operations and safety. Vol. 2
- Imprint Pagination
- 814 p.
- Journal Page Range
- p. 54B1-54B6
- Report number
- INIS-XA-N--081
Conference
- Title
- 4. international topical meeting on nuclear thermal hydraulics, operations and safety
- Dates
- 5-8 Apr 1994
- Place
- Taipei, Taiwan (China)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 35097950
- Subject category
- S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CRITICAL HEAT FLUX; FLUID FLOW; PRESSURE DEPENDENCE; PRESSURE RANGE MEGA PA 01-10; WATER
- Descriptors DEC
- HEAT FLUX; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; PRESSURE RANGE; PRESSURE RANGE MEGA PA
Optional Information
- Notes
- This record replaces 35095683; 18 refs, 10 figs