Published July 2018 | Version v1
Journal article

Air Water Loop for investigation of flow dynamics in a steam drum: Carryover experiments and CFD simulation

  • 1. Homi Bhabha National Institute, Anushaktinagar, Mumbai 400094 (India)
  • 2. Reactor Engineering Division, Bhabha Atomic Research Centre, Trombay, Mumbai 400085 (India)
  • 3. Department of Chemical Engineering, Institute of Chemical Technology, Matunga, Mumbai 400019 (India)

Description

Highlights: • Experiments with air-water shows near surface entrainment of the order of 400–600%. • Droplets generated at interface follow Upper Limit Log Normal (ULLN) distribution. • Within the operating range, maximum droplet diameter measured was of 2.7 mm size. • Kataoka & Ishii correlation predicts higher entrainment rates when compared to CFD. - Abstract: Advanced Heavy Water Reactor (AHWR) being developed in India is a vertical pressure tube type boiling water reactor. In case of AHWR the steam-water two-phase flow from the core is separated in horizontal steam drums purely due to gravity i.e. density difference between the steam and water. This simple principle eliminates the need for mechanical separators and associated system pressure drop. However, the separation efficiency is affected by the entrainment phenomenon, i.e. conveyance of water droplets by the separated steam out of the drum i.e. carryover. Carryover estimation for new equipment with existing empirical correlations may not be reliable and experimental investigations in relevant geometries are necessary. In the present work carryover process has been investigated in a test facility known as Air-Water Loop (AWL). The facility aims at simulation of gravity separation of two-phase flows relevant to AHWR steam drum, using air-water mixture. During the experiments, carryover at operating levels closer to exit has been measured. AWL also has a facility for optical measurements using high speed camera. Measurements on droplet size distribution have been carried out with shadowgraph technique at different operating levels. The present work also involves the analysis of carryover using 3-D Euler-Lagrangian simulations with OpenFOAM based solver.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2018.04.012

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2018.04.012;
PII
S0029549318304321;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
333
Journal Page Range
p. 145-160
ISSN
0029-5493
CODEN
NEDEAU

Optional Information

Notes
© 2018 Elsevier B.V. All rights reserved.