Vapor Pressure and Temperature Analyses on a Gravity-Assisted Wrapped Screen Wick Annular Heat Pipe

Daniel Orea, N. K. Anand, Yassin A. Hassan

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

Abstract

Internal pressure and temperature measurements were made on a wrapped screen mesh wick annular heat pipe using distilled water as the working fluid. High-resolution pressure transducers were connected to two probes and inserted into the evaporator and condenser regions of the heat pipe's vapor flow passage to gather local static and differential pressure information. Optical fiber distributed temperature sensors (OFDTS) and K-type thermocouples were used to collect internal and external surface temperature measurements at various axial locations. With the heat pipe in the vertical orientation (gravity-assisted), simultaneous measurements of the vapor pressure, temperature, and external surface temperature were conducted for heat loads of 25 W, 50 W, and 75 W. The vapor flow frictional coefficient was calculated based on the data at multiple vapor flow Reynolds numbers, which correspond to a given input power. Ad-ditional time-frequency analysis was performed on the pressure drop information to gain insight on the flow behavior, characteristics, and infer regime occurring within the vapor core region of the heat pipe. The results of these pressure drop measurements and frictional coefficients provide a valuable database that supports the advancement of heat pipe modeling and validation for advance reactors applications such as, small modular reactors (SMR), and microreactors.

Original languageEnglish
Title of host publicationProceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
PublisherAmerican Nuclear Society
Pages2549-2560
Number of pages12
ISBN (Electronic)9780894487934
DOIs
StatePublished - 2023
Externally publishedYes
Event20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023 - Washington, United States
Duration: Aug 20 2023Aug 25 2023

Publication series

NameProceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023

Conference

Conference20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
Country/TerritoryUnited States
CityWashington
Period08/20/2308/25/23

Funding

The authors would like to thank Dr. Joseph Seo and Ojasvin Arora for their guidance during the experiments, as well as Dr. Craig Menezes and Reynaldo Chavez for their technical advise in the data post-processing and analyzing. This study was supported by the Nuclear Regulatory Commission (NRC) as a co-joint project with the University of Texas-Arlington (UTA) and Texas A&M University (TAMU) (Award Number 3131002M0050).

Keywords

  • Heat Pipe
  • Pressure
  • Temperature
  • Wavelet

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