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The Research of PHWR Reactor Feeder Flow Measurement

[+] Author Affiliations
Xin Sheng

CNNC Nuclear Power Operations Management Co., Ltd., Haiyan, Zhejiang, China

Paper No. ICONE21-16468, pp. V001T01A037; 9 pages
  • 2013 21st International Conference on Nuclear Engineering
  • Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications
  • Chengdu, China, July 29–August 2, 2013
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-5578-2
  • Copyright © 2013 by ASME


PHWR (also known as CANDU) primary heat transport (PHT) system is to make the pressurized heavy water through the reactor fuel channel, take away the heat produced by the fission of uranium fuel (i.e. fuel cooling), through the reactor feeder pipes, into the Steam Generator. PHWR reactor feeder flow value are a very important parameters, which are stable and meets the requirements of the design, plays an important role in the NPP safe operation.

This paper summarize the Qinshan CANDU reactor feeder flow measurement in practice, based on the feeder flow measurement principle and measurement data are analyzed and studied, including feeder flow measurement stages, site preparation of material and equipment, data measurement methods, data analysis methods, dealing with flow measurement uncertainties, and some other key point need to be attention.

The Qinshan CANDU reactor feeder flow measurement schedules create the same type of CANDU units commissioning records in the world, which is not only shorten the commissioning critical path time, but also laid the foundation for the safety operation. The reasons for the Qinshan success are also to analyze in this article.

Finally, this paper based on the experience of Qinshan CANDU feeder flow measurement, put forward some suggestions on organization and implementation to minimize human error and increase its efficiency, and hope for the help on the similar work area in the future.

Copyright © 2013 by ASME



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