Published 2004 | Version v1
Book

Influence of dissolved gas concentration on subcooled flow boiling critical heat flux in short vertical tube

  • 1. Institute of Advanced Energy, Kyoto (Japan)
  • 2. Department of Energy Science and Technology, Kyoto University, Kyoto (Japan)
  • 3. National Institute for Fusion Science, Toki, Gifu (Japan)

Description

The objectives of the present study is threefold. First, it is to measure the CHF (critical heat flux) on the rough and smooth finished inner surfaces of short vertical tubes with 3 mm inner diameter and 66.5 mm heated length for a wide range of dissolved gas concentrations (ranging from saturated condition to near 0 ppm) and flow velocity. Secondly, it is to confirm the applicability of CHF correlations against outlet and inlet subcooling for low dissolved gas concentration region. Thirdly,it is to discuss the mechanisms of subcooled flow boiling heat flux in a short vertical tube. It appears that first, the CHF data under the saturated vapor pressurization by using the pressurizer are in good agreement with the values calculated by the CHF correlations against outlet and inlets subcooling, based on the experimental data under the N2 gas pressure previously obtained in the whole experimental range. Secondly, the CHF for the rough finished inner surface test tube is kept almost constant for dissolved oxygen concentrations ranging from 6.59 to 0.0265 ppm and for flow velocities ranging from 4.0 to 13.3 m/s. Thirdly, the CHF for smooth inner surface and for higher flow velocities are about 10% or more lower than that for the rough surface. And fourthly, no direct transition to film boiling was observed on the smooth surface used here even at the lowest dissolved oxygen concentration

Part of:
Proceedings of the 12. international conference on nuclear engineering. Volume 3

Additional details

Publishing Information

Publisher
American Society of Mechanical Engineers - ASME
Imprint Place
New York (United States)
ISBN
0-7918-4689-X
Imprint Title
Proceedings of the 12. international conference on nuclear engineering. Volume 3
Imprint Pagination
893 p.
Journal Page Range
p. 505-514

Conference

Title
12. international conference on nuclear engineering - ICONE 12
Dates
25-29 Apr 2004
Place
Arlington - Virginia (United States)

INIS

Country of Publication
United States
Country of Input or Organization
France
INIS RN
38116523
Subject category
S42: ENGINEERING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BENCH-SCALE EXPERIMENTS; CORRELATIONS; CRITICAL HEAT FLUX; HEAT TRANSFER; PARAMETRIC ANALYSIS; SUBCOOLED BOILING; TWO-PHASE FLOW
Descriptors DEC
BOILING; ENERGY TRANSFER; FLUID FLOW; HEAT FLUX; PHASE TRANSFORMATIONS

Optional Information

Notes
22 refs.