Published September 2002 | Version v1
Journal article

An investigation on steam-water two-phase forced convection boiling heat transfer in helical-coiled tubes

  • 1. Northeast China Inst. of Electric Power Engineering, Jilin (China)
  • 2. Xi'an Jiaotong Univ., Xi'an (China)

Description

Two-phase flow forced convection boiling heat transfer on helical-coiled tubes has been systematically studied. The experiments have been done on high pressure water loop in Xi'an Jiaotong University. The test condition is as follows: system pressures 6.0 to 11 MPa, mass velocity 400 to 1200 kg/(m2·s), helical diameter 1.37 m and helical angles 3.94 degree. Two-phase forced convection heat transfer coefficients are correlated as function of Lockhart-Martinelli parameter. Subcooling water and superheated vapor forced convection heat transfer coefficient are also presented and compared with other literatures

Additional details

Publishing Information

Journal Title
Chinese Journal of Nuclear Science and Engineering
Journal Volume
22
Journal Issue
3
Journal Page Range
p. 217-219, 228
ISSN
0258-0918

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
34053670
Subject category
S42: ENGINEERING;
Resource subtype / Literary indicator
Numerical Data
Descriptors DEI
BENCH-SCALE EXPERIMENTS; BOILING; EXPERIMENTAL DATA; FORCED CONVECTION; HEAT TRANSFER; SPIRAL CONFIGURATION; STEAM GENERATORS; TEST FACILITIES; TUBES; TWO-PHASE FLOW
Descriptors DEC
BOILERS; CONFIGURATION; CONVECTION; DATA; ENERGY TRANSFER; FLUID FLOW; HEAT TRANSFER; INFORMATION; MASS TRANSFER; NUMERICAL DATA; PHASE TRANSFORMATIONS; VAPOR GENERATORS