The experiments were performed on the test loop HRTL-5, which simulates geometry and system design of the 5-MW Nuclear Heating Reactor developed by the Institute of Nuclear Energy Technology, Tsinghua University. Because of the difference of the geometry design and operating conditions between the heating reactor and the boiling water reactor, the flow behavior presents great differences too, some of which haven’t been deeply studied so far. Results show that in heating reactor, sub-cooled boiling, condensation and flashing play an important role on the flow instabilities of the natural circulation system. Correspondingly, geysering instability, flashing instability, and flow excursion are the very typical instabilities occurring in the primary loop of HRTL-5, which are different from those in boiling water reactor conditions. The compressibility of the steam space on the top of the primary loop has also great influence on the instability of the natural circulation system.
Skip Nav Destination
10th International Conference on Nuclear Engineering
April 14–18, 2002
Arlington, Virginia, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-3597-9
PROCEEDINGS PAPER
Description of Typical Flow Instabilities in the Natural Circulation System
Shengyao Jiang,
Shengyao Jiang
Tsinghua University, Beijing, P. R. China
Search for other works by this author on:
Xingtuan Yang,
Xingtuan Yang
Tsinghua University, Beijing, P. R. China
Search for other works by this author on:
Youjie Zhang
Youjie Zhang
Tsinghua University, Beijing, P. R. China
Search for other works by this author on:
Shengyao Jiang
Tsinghua University, Beijing, P. R. China
Xingtuan Yang
Tsinghua University, Beijing, P. R. China
Youjie Zhang
Tsinghua University, Beijing, P. R. China
Paper No:
ICONE10-22037, pp. 41-51; 11 pages
Published Online:
March 4, 2009
Citation
Jiang, S, Yang, X, & Zhang, Y. "Description of Typical Flow Instabilities in the Natural Circulation System." Proceedings of the 10th International Conference on Nuclear Engineering. 10th International Conference on Nuclear Engineering, Volume 3. Arlington, Virginia, USA. April 14–18, 2002. pp. 41-51. ASME. https://doi.org/10.1115/ICONE10-22037
Download citation file:
6
Views
Related Proceedings Papers
Related Articles
The Effect of Inlet Subcooling on the Critical Heat Flux for Downward Flow With Upstream Compressibility
J. Heat Transfer (May,1995)
The Onset of Flow Instability for Downward Flow in Vertical Channels
J. Heat Transfer (August,1996)
On the Dominant Unstable Wavelength During Film Boiling on a Horizontal Cylinder of Small Diameter
J. Heat Transfer (May,1993)
Related Chapters
Flow Boiling
Thermal Management of Microelectronic Equipment
Saturated Boiling with Forced Flow
Two-Phase Heat Transfer
Critical Heat Flux in Flow Boiling
Two-Phase Heat Transfer