Published 2009 | Version v1
Miscellaneous

Numerical calculations on countercurrent gas-liquid flow in a PWR hot leg. (2) Steam-water flow under PWR plant conditions

  • 1. Institute of Nuclear Safety System, Inc., Mihama, Fukui (Japan)
  • 2. Kobe University, Kobe, Hyogo (Japan)

Description

In order to improve the countercurrent flow model of a transient analysis code, countercurrent air-water tests were previously conducted using a 1/15th scale model of the PWR hot leg at Kobe University. Then numerical calculations were made of the test results using the thermal-hydraulic analysis code FLUENT6.3.26 and an Euler-Euler model. The calculated flow patterns in the hot leg were quite similar to the observed results, and the calculated CCFL (countercurrent flow limitation) characteristics agreed well with the measured data. In the present study, we carried out numerical calculations for steam-water flow under PWR plant conditions. The calculated flow patterns in the hot leg were similar to the observed results in the 1/15th scale air-water tests. Furthermore, the calculated CCFL characteristics correlated with Wallis parameters agreed well with the data by the 1/15th scale air-water tests and the full-scale steam-water UPTF tests. The results indicate that the correlations used for the gas-liquid interfacial friction are valid. (author)

Part of:
NURETH-13: Proceedings of the 13th international topical meeting on nuclear reactor thermal hydraulics

Additional details

Publishing Information

Imprint Title
NURETH-13: Proceedings of the 13th international topical meeting on nuclear reactor thermal hydraulics
Imprint Pagination
[4617 p.]
Journal Page Range
[9 p.]

Conference

Title
13. international topical meeting on nuclear reactor thermal hydraulics
Acronym
NURETH-13
Dates
27 Sep - 2 Oct 2009
Place
Kanazawa, Ishikawa (Japan)

Optional Information

Notes
Available as CD-ROM Data in PDF format, Folder Name: FullPaper, Paper ID: N13P1040.pdf; 17 refs., 7 figs.