Abstract
The SIRIUS-N facility was designed and constructed for highly accurate simulation of core-wide and regional instabilities of the BWR. A real-time simulation was performed in the digital controller for heat conduction in a fuel-rod and modal point kinetics of reactor neutronics using measured void fractions in reactor core sections of the thermal-hydraulic loop. In order to estimate decay ratios, an auto-regressive method has been successfully applied for time series data of the core inlet flow rate. Experiments were conducted with the SIRIUS-N facility for the rated operating condition of 3.13GWt natural circulation BWR. Channel and regional stability decay ratios were determined to be 0.38 and 0.54, respectively, which indicates sufficient margin for the instabilities. Experiments were extended to evaluate the stability sensitivity of design parameters such as the power profile, void reactivity coefficients, core inlet sub-cooling, and the fuel rod time constant.
| Original language | English |
|---|---|
| Pages (from-to) | 341-350 |
| Number of pages | 10 |
| Journal | Journal of Nuclear Science and Technology |
| Volume | 42 |
| Issue number | 4 |
| DOIs | |
| Publication status | Published - 2005 Apr |
| Externally published | Yes |
Keywords
- BWR type reactors
- Channel stability
- Core-wide stability
- Density wave oscillations
- Natural circulation
- Regional stability
- Stability
- Void-reactivity feedback
ASJC Scopus subject areas
- Nuclear and High Energy Physics
- Nuclear Energy and Engineering