Published September 2002
| Version v1
Journal article
An investigation on steam-water two-phase forced convection boiling heat transfer in helical-coiled tubes
Creators
- 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