Abstract
For advanced nuclear power plant designs including Sodium-cooled Fast Reactors (SFRs), High Temperature Gas-cooled Reactors (HTGRs), and Small Modular Reactors (SMRs), helically coiled steam generators (HCSGs) have been under consideration with their increased heat transfer capability within a compact design. A five-layer helical coil steam generator model was constructed with each layer facing adjacent layers that coil against it. A test section (1/16 of a full circular geometry) was installed in a flow loop, and four regions in the middle of the test section were investigated using particle image velocimetry (PIV). Experiments conducted focused to capture the velocity flow field in each region at approximately Re ≈ 3,600 (inlet condition at 0.218 m/s). A preliminary Reynolds averaged analysis was performed in a previous work. In the current work, additional experimental data was obtained after that, and proper orthogonal decomposition (POD) was applied to study the high energy mode coherent flow structures.
Original language | English (US) |
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Pages | 5894-5904 |
Number of pages | 11 |
State | Published - 2019 |
Event | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019 - Portland, United States Duration: Aug 18 2019 → Aug 23 2019 |
Conference
Conference | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019 |
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Country/Territory | United States |
City | Portland |
Period | 8/18/19 → 8/23/19 |
All Science Journal Classification (ASJC) codes
- Nuclear Energy and Engineering
- Instrumentation