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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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Part of:
Proceedings of the fourth international topical meeting on nuclear thermal hydraulics, operations and safety. Vol. 2

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