| Popis: |
Under fault conditions, it is important maintain the safety of nuclear power plant. Meanwhile, it is also necessary to generate its maximum power output, especially for small modular reactors, to improve the economy. The helical-coiled once-through steam generator of IRIS is chosen as a research object. The moving boundary method is applied to derive its thermal-hydraulic model. It is divided into subcooled region, boiling region, and superheated region. Through comparisons between calculated results and design data, the model is proved to be accurate enough for the optimization study. Sensitivity analysis is performed to investigate the influences on the thermal power from the steam generator key operation parameters. Feedwater flow rate and average coolant temperature are selected as optimized variables, and the thermal power is chosen as the objective function. The constraints on the tube temperature, reactor outlet temperature, circulation ratio, and reactor inlet temperature are chosen as limits. Polynomial fit algorithm is applied to derive their relationship. Optimization is obtained to find its maximal value. The results of optimization under the fault conditions are reasonable for practical application. Finally, hybrid algorithm is proposed as an alternate method for further study. |
