Abstract
By using resistivity-temperature correlation, Joule’s Law, resistivity equation and Piecewise Cubic Hermite Interpolating Polynomial (PCHIP) functions, Joule heating heat flux profiles of heat transfer of upward supercritical water flow in annular tube are modelled. The resistivity-temperature correlation of the annular tube is correlated according to the experiment data. By using the correlation and wall temperature profile, the electrical resistivity profile is estimated. The electrical resistivity profile is modelled by PCHIP functions, and by numerical integration, the total resistance of the tube is approximated. On the other hand, with the known experiment power supply, Joule's Law is used to calculate the root means square current through the annular tube. With the resistivity equation, discrete local heat flux can be calculated. Heat flux profile along the heated surface is therefore modelled by PCHIP functions. Wall temperature profile is calculated with FLUENT 21 using the Shear Stress Transport (SST) k-ω turbulence model. The result is compared with the Razumovskiy et al. experiment dataset. Using the PCHIP-modelled Joule heating profiles, the calculated wall temperature for both the NHT and DHT regimes falls within the experimental error margin of ± 3.2%. Using constant heat flux profiles, the upstream and downstream wall temperatures are overestimated and underestimated, respectively, but the predicted temperature is still within ± 3.2% error margin under the NHT regime. This study demonstrated that CFD can mimic the experiment heat flux condition with adequate results. A new approach with the use of PCHIP is established. This approach can better the CFD estimation of supercritical heat transfer, especially for the DHT which has significant heat flux deviation.
| Original language | English |
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| Publication status | Published - Sept 2022 |
| Event | 13th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-13) - On-line, Hsinchu, Taiwan Duration: 5 Sept 2022 → 10 Sept 2022 http://www.nuthos-13.org |
Conference
| Conference | 13th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-13) |
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| Country/Territory | Taiwan |
| City | Hsinchu |
| Period | 5/09/22 → 10/09/22 |
| Internet address |
Research Keywords
- Deteriorated Heat Transfer (DHT)
- Piecewise Cubic Hermite Interpolating Polynomial (PCHIP)
- Supercritical Water (SCW)
- Vertical Annular Tube Flow With Ribs
- Joule Heating