Pressure drop measurements across a Helical Coil Steam Generator configuration

Marilyn Delgado, Samuel Lee, Saya Lee, Yassin A. Hassan

Research output: Chapter in Book/Report/Conference proceedingConference contribution

4 Scopus citations

Abstract

The primary heat transport loop heat exchanger within a Very-High Temperature Reactor (VHTR) is most commonly a Helical Coil Steam Generator (HCSG). This design has been regarded as having increased heat transfer within a smaller design in comparison to other heat exchangers. The fluidic heat transfer properties of the HCSG is still under evaluation in tangent with HTRs due to its complex design. Heat transfer between these layers relies heavily on their relative location and fluidic properties. A model was constructed to study the pressure field on a rod's surface as well as across multiple layers of helically facing tubes. Experiments focused on evaluating the impact relative geometry played on the overall pressure drop of the test section with inlet fluid velocity ranging from 0 to 3 m/s. A study to compare the experimental results with the Gaddis-Gnielinski Correlative theoretical values of pressure drop in tube bundles shows that the complex helical geometry results in pressure drops similar to that of fully developed rod bundle although the test facility is comprised of two half rod helical coils.

Original languageEnglish (US)
Title of host publicationInternational Topical Meeting on High Temperature Reactor Technology, HTR 2016
PublisherAmerican Nuclear Society
Pages1009-1014
Number of pages6
ISBN (Electronic)9780894487323
StatePublished - 2016
Event8th International Topical Meeting on High Temperature Reactor Technology, HTR 2016 - Las Vegas, United States
Duration: Nov 6 2016Nov 10 2016

Publication series

NameInternational Topical Meeting on High Temperature Reactor Technology, HTR 2016

Conference

Conference8th International Topical Meeting on High Temperature Reactor Technology, HTR 2016
CountryUnited States
CityLas Vegas
Period11/6/1611/10/16

All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering
  • Energy Engineering and Power Technology

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