Simulation of subcooled boiling and critical heat flux in uniformly heated tubes
Creators
- 1. Department of Engineering Physics, Tsinghua University, Beijing (China)
- 2. Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu (China)
Description
Based on Eulerian two-fluid framework and non-equilibrium subcooled boiling model, the numerical model is established to simulate the subcooled boiling. This model is used to simulate the subcooled flow and CHF of DNB type in uniformly heated tubes. The numerical model is proved correct by comparing to the subcooled flow experiment of Bartolomei. The boiling curves is calculated, and it is suggested to treat the first point in the critical area of boiling curves as the criterion of DNB. 12 CHF points drawn from the latest 2006 CHF look-up table are simulated. These 12 points are chosen with different mass flux, pressure or local equilibrium quality, but all are under high pressures and high mass flux. The CHF predicted confirm well to the experiment and the location that CHF occur is also well captured. (authors)
Additional details
Publishing Information
- Journal Title
- Nuclear Power Engineering
- Journal Volume
- 36
- Journal Issue
- 1
- Journal Page Range
- p. 168-172
- ISSN
- 0258-0926
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 48083751
- Subject category
- S42: ENGINEERING;
- Descriptors DEI
- COMPUTERIZED SIMULATION; CRITICAL HEAT FLUX; DEPARTURE NUCLEATE BOILING; DIAGRAMS; EQUILIBRIUM; FLUIDS; MASS; PRESSURE RANGE MEGA PA 10-100; SUBCOOLED BOILING; TUBES
- Descriptors DEC
- BOILING; HEAT FLUX; INFORMATION; NUCLEATE BOILING; PHASE TRANSFORMATIONS; PRESSURE RANGE; PRESSURE RANGE MEGA PA; SIMULATION
Optional Information
- Notes
- 4 figs., 1 tab., 9 refs.