Published September 1995 | Version v1
Report

Bubble behaviour and mean diameter in subcooled flow boiling

  • 1. McMaster Univ., Hamilton, Ontario (Canada)

Description

Bubble behaviour and mean bubble diameter in subcooled upward flow boiling in a vertical annular channel were investigated under low pressure and mass flux conditions. A high speed video system was used to visualize the subcooled flow boiling phenomenon. The high speed photographic results indicated that, contrary to the common understanding, bubbles tend to detach from the heating surface upstream of the net vapour generation point. Digital image processing technique was used to measure the mean bubble diameter along the subcooled flow boiling region. Data on the axial area-averaged void fraction distributions were also obtained using a single beam gamma densitometer. Effects of the liquid subcooling, applied heat flux and mass flux on the mean bubble size were investigated. A correlation for the mean bubble diameter as a function of the local subcooling, heat flux and mass flux was obtained

Additional details

Publishing Information

Imprint Title
Proceedings of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7. Sessions 17-24
Imprint Pagination
825 p.
Journal Page Range
p. 3175-3196.
Report number
NUREG/CP--0142-Vol.4

Conference

Title
7. international meeting on nuclear reactor thermal hydraulics.
Dates
10-15 Sep 1995.
Place
Saratoga, NY (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
27019406
Subject category
S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BOILERS; BUBBLES; FLOW VISUALIZATION; FLUID MECHANICS; HEAT EXCHANGERS; HEAT TRANSFER; HYDRAULICS; REACTOR COOLING SYSTEMS; REFRIGERATING MACHINERY; SUBCOOLED BOILING; TWO-PHASE FLOW; VOID FRACTION
Descriptors DEC
BOILING; COOLING SYSTEMS; ENERGY TRANSFER; EQUIPMENT; FLUID FLOW; MACHINERY; MECHANICS; PHASE TRANSFORMATIONS; REACTOR COMPONENTS

Optional Information

Secondary number(s)
CONF-950904--Vol.4.