Abstract
A new database of two-phase natural circulation with a vertical annulus heated and riser section is developed by the Multiphase Thermo-fluid Dynamics Laboratory (MTDL) at the University of Illinois at Urbana-Champaign, focusing on such two-phase phenomena as boiling, condensing, and flashing under natural circulation in a vertical section. In addition to flow parameters, local two-phase measurements such as void fraction, interfacial area concentration, gas velocity, and Sauter mean diameter are measured at various axial locations on the annular test section. Furthermore, the area-averaged and void-weighted measurements are calculated to provide an overview on the evolution of two-phase parameters along the test section. The dataset is valuable for the validation of one-dimensional system codes as well as multi-dimensional fluid dynamics codes. Several representative cases are presented in this work to discuss the effect of flow parameters on the formation and evolution of the natural circulation in the flow loop.
Original language | English |
---|---|
Pages (from-to) | 124-136 |
Number of pages | 13 |
Journal | Progress in Nuclear Energy |
Volume | 116 |
DOIs | |
State | Published - Sep 2019 |
Externally published | Yes |
Funding
This material is based upon work supported by the Department of Energy under award number DE-NE0008573 .
Funders | Funder number |
---|---|
U.S. Department of Energy | DE-NE0008573 |
Keywords
- Annulus
- Natural circulation
- Steam-water flow
- Two-phase