Published 1997 | Version v1
Book Metadata-only

Critical heat flux with subcooled boiling of water at low pressure

Creators

  • 1. China Inst. of Atomic Energy, Beijing, BJ (China)

Description

The critical heat flux experiment has been performed in round tubes of 10 and 16 mm in diameter with different heating length, covering the range of pressure 1.5-16.7 bar, velocity 1.4-15.4 m/s and exit subcooling 30-136 K. The experimental data and empirical correlations are presented. Based on the results an evaluation of some correlations and 1995 CHF look-up table is made. For the conditions tested the effect of diameter on the critical heat flux is found to be related to the liquid velocity. (author)

Part of:
Eighth international topical meeting on nuclear reactor thermal-hydraulics

Additional details

Publishing Information

Publisher
Atomic Energy Society of Japan
Imprint Place
Tokyo (Japan)
Imprint Title
Eighth international topical meeting on nuclear reactor thermal-hydraulics
Imprint Pagination
1890 p.
Journal Page Range
p. 958-964

Conference

Title
8. international topical meeting on nuclear reactor thermal-hydraulics
Acronym
NURETH-8
Dates
30 Sep - 4 Oct 1997
Place
Kyoto (Japan)

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
30016298
Subject category
S42: ENGINEERING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BOILING; CORRELATIONS; CRITICAL HEAT FLUX; HEATING; SUBCOOLING; TUBES; VELOCITY; WATER
Descriptors DEC
COOLING; HEAT FLUX; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; PHASE TRANSFORMATIONS

Optional Information

Notes
Imprint:Published in 3 volumes