Abstract
The cross-correlation flow measurement technique, applied for measuring the coolant flow rate in a nuclear reactor, was calibrated with the use of numerical simulations of turbulent flow. The three-dimensional domain was collapsed into two dimensions. With a two-dimensional calculation of steady-state flow with transient thermal characteristics the response of thermocouples to a temperature variation was calculated. By cross-correlating the calculated thermocouple responses, the link between total flow rate and measured transit times was made. The reliability of the calibration was estimated at ±4.6%. In addition, a measured velocity profile effect was successfully predicted.
| Original language | English |
|---|---|
| Pages (from-to) | 143-158 |
| Number of pages | 16 |
| Journal | International Journal of Numerical Methods for Heat & Fluid Flow |
| Volume | 4 |
| Issue number | 2 |
| DOIs | |
| Publication status | Published - 1 Feb 1994 |
| Externally published | Yes |
Keywords
- Cross-correlation flow measurement
- Thermoflow
- Transient flow simulation