Published May 2015 | Version v1
Miscellaneous

Experimental study on the local interfacial characteristics of subcooled flow boiling under inclined condition

  • 1. CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology, Chengdu (China)

Description

Subcooled flow boiling in inclined tube occurs widely in many industries and applications. An experimental study on the local interfacial characteristics of subcooled flow boiling was carried out under vertical and inclined conditions. The test section is a circular tube (i.d. 24 mm) of which axial heated length is 1 m. A double-sensor optical probe was used to investigate the radial distribution of interfacial parameters including local void fraction, bubble frequency, interfacial velocity, Sauter bubble diameter and Interfacial Area Concentration (IAC). The range of heat flux and mass flux are 140-900 kW/m2 and 200-800 kg/m2s, respectively. The inclination angles are 5deg, 10deg, 20deg, 30deg, and the polar angle between measurement direction and inclination direction in the probe measurement cross-section are 0deg, 45deg, 90deg. From the test, the local interfacial parameters were measured at 15 radial locations at probe elevation. Based on these data obtained in the previous test loop, the influence of flow condition and inclination angle on the profiles of local interfacial parameters was discussed. (author)

Part of:
Proceedings of the 23th international conference on nuclear engineering (ICONE-23)

Additional details

Publishing Information

Imprint Title
Proceedings of the 23th international conference on nuclear engineering (ICONE-23)
Imprint Pagination
[3737 p.]
Journal Page Range
[12 p.]

Conference

Title
23. international conference on nuclear engineering
Acronym
ICONE-23
Dates
17-21 May 2015
Place
Chiba (Japan)

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
48023505
Subject category
S42: ENGINEERING;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
ADIABATIC PROCESSES; BUBBLES; FLOW VISUALIZATION; HEAT FLUX; INCLINATION; NUCLEAR POWER PLANTS; REFRIGERATION; SPATIAL DISTRIBUTION; SUBCOOLED BOILING; SUBCOOLING; THERMAL HYDRAULICS; TUBES; TWO-PHASE FLOW; VOID FRACTION
Descriptors DEC
BOILING; COOLING; DISTRIBUTION; FLUID FLOW; FLUID MECHANICS; HYDRAULICS; MECHANICS; NUCLEAR FACILITIES; PHASE TRANSFORMATIONS; POWER PLANTS; THERMAL POWER PLANTS

Optional Information

Notes
Available as DVD-ROM Data in PDF format. Folder Name: FullPaper; Paper ID: ICONE23-1710.pdf; 19 refs., 8 figs., 1 tab.