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Development of Nuclear-Specific Coriolis Flowmeters Based on the Straight-Tube Technology

[+] Author Affiliations
Tao Wang, Yousif Hussain

KROHNE Ltd., Wellingborough, UK

Paper No. ICONE18-30055, pp. 821-826; 6 pages
  • 18th International Conference on Nuclear Engineering
  • 18th International Conference on Nuclear Engineering: Volume 1
  • Xi’an, China, May 17–21, 2010
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-4929-3
  • Copyright © 2010 by ASME


The application of Coriolis flowmeters to various industries has been expanding since they were successfully introduced in the market some 30 years ago. This paper specifically reports the development of Coriolis flowmeters for the nuclear industry based on the latest straight-tube technology. An advanced numerical method combining the strength of commercially available simulation packages and in-house theoretical work was used in the development. This includes the initial prediction of flow sensitivity using the fluid-structure interaction theory for straight flow tubes to ensure sufficient measurement accuracy under various process conditions. It also includes further detailed analysis of the entire flowmeter to make sure its natural frequencies away from the seismic frequency range due to nuclear application safety reasons. Furthermore, a new calibration and testing procedure is reported in this paper, which includes the normal calibration condition and also simulates possible process conditions during the nuclear applications (e.g. varying fluid temperature). Additionally, calculations based on the Design by Formula approach according to the governing codes, particularly ASME Boiler and Pressure Vessel Code, Section III, are also reported. These simplified calculations are of significant importance for Coriolis flowmeters to be applied to nuclear applications. Finally, a case study which involved significant collaboration with a well-known safety-related solution provider in the nuclear industry is described, where Coriolis flowmeters were required to provide accurate measurement for the boric acid make-up subsystem in a pressurised water reactor system. Design checks and special considerations for the fabrication and testing according to the rules of ASME Code Section III together with a quality assurance procedure as described in the case study showed that the developed Coriolis flowmeter can meet the specific requirements of nuclear applications in terms of both measurement performance and safety concerns.

Copyright © 2010 by ASME
Topics: Flowmeters



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