Nuclear power is becoming a very important low-carbon option to achieve electricity production. As proved in many other process plants, Coriolis flowmeters have a number of advantages for measuring process parameters, typically flow and density. This paper looks specifically at the development and application of Coriolis flowmeters for nuclear power plants. In particular, the requirements of typical nuclear applications and the design considerations to meet these requirements are discussed. Using ASME Boiler and Pressure Vessel Code, Section III, as the governing code, design of straight-tube Coriolis flowmeters is described, which resulted a series of products with ASME N-Stamp certificates.
References
1.
ASME Boiler and Pressure Vessel Committee, Subcommittee on Nuclear Power, “ASME Boiler & Pressure Vessel Code III, Division I — Subsection ND, Class 3 Components, Rules for Construction of Nuclear Facility Components,” Jul. 2007.
2.
WangT.HussainY., “Latest research and development of twin-straight tube Coriolis mass flowmeters,”Sens. Rev.Vol. 27, 2007, pp. 43–47.
3.
RaoK., Companion Guide to the ASME Boiler and Pressure Vessel Code, 2002.
4.
NRC, “Seismic Design Classification, NRC Regulatory Guide 1.29,” Mar. 2007.
5.
WangT.HussainY., “Development of Nuclear-specific Coriolis Flowmeters Based on the Straight-tube Technology,”Proceedings of the 18th International Conference on Nuclear Engineering, Xi'an, China: ASME, 2010.
