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 language | English |
---|---|
Title of host publication | Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023 |
Publisher | American Nuclear Society |
Pages | 2549-2560 |
Number of pages | 12 |
ISBN (Electronic) | 9780894487934 |
DOIs | |
State | Published - 2023 |
Externally published | Yes |
Event | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023 - Washington, United States Duration: Aug 20 2023 → Aug 25 2023 |
Publication series
Name | Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023 |
---|
Conference
Conference | 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023 |
---|---|
Country/Territory | United States |
City | Washington |
Period | 08/20/23 → 08/25/23 |
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