Published December 2017 | Version v1
Journal article

Scaled experiment investigating sonomechanically enhanced inert gas sparging mass transfer

  • 1. Department of Nuclear Engineering, University of New Mexico, MSC01 1120, 1 University of New Mexico, Albuquerque, NM 87131-0001 (United States)
  • 2. Center for Nondestructive Evaluation, Iowa State University, Ames, IA 50011 (United States)

Description

Highlights: • Scaled inert gas sparging experiment investigating ultrasonic enhancement was performed. • The surrogate fluid for the fluoride salt (flibe) was a water/glycerol mixture. • The ultrasonic enhancement shows an improvement in the mass transfer performance. • Improved existing mass transfer correlation to include ultrasonic enhancement. - Abstract: One of the leading advanced reactor concepts is the fluoride salt high temperature reactor (FHR) currently under investigation. This design utilizes a fluoride molten salt, flibe (2LiF/BeF2), as the primary coolant. One challenge of employing flibe as a coolant is the production and release of tritium. The FHR community is currently investigating various techniques to solve this tritium management challenge. One of the methods investigated is inert gas sparging which has been investigated during the Molten Salt Reactor Experiment (MSRE) in the 1960's and 1970's. To enhance the efficiency of this technique, high power ultrasonics can be employed to sonomechanically enhance the mass transfer performance. Initial experimental studies coupling ultrasonics and inert gas sparging have been performed in the scaled ultrasonic mass transfer (SUMATRA) experiment. The scaling was done by matching the Sc between a water/glycerol mixture and flibe at FHR temperatures. The SUMATRA experiment evaluated the performance of inert gas sparging with and without ultrasonic enhancement. The results show a significant performance enhancement due to the sonomechanical effect which is contributed to an increase in the diffusive mass transfer contribution due to bubble breakup and the subsequent increase interfacial area.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2017.08.016

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2017.08.016;
PII
S0029549317303904;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
324
Journal Page Range
p. 171-180
ISSN
0029-5493
CODEN
NEDEAU

Optional Information

Notes
© 2017 Elsevier B.V. All rights reserved.