超临界水冷堆核热耦合计算研究

Study on Neutronic-Thermohydraulic Coupling Calculation of SCWR

以美国超临界水堆(SCWR)设计为研究对象,开发超临界水堆的物理-热工耦合计算程序。该计算程序采用Dragon和Donjon直接耦合计算,提高计算精度和速度;并在功率迭代中引入松弛因子,通过部分迭代法解决传统迭代方法不收敛的问题。轴向温度和密度分布的计算结果验证了程序的有效性和准确性。

Based on the U.S. SCWR design, the thermohydraulic module is coupled with neutronic codes Dragon and Donjon directly, to develop a calculation codes for neutronic/thermohydraulic coupling, which can improve the accuracy and efficiency of coupling calculation. The relaxation factor is introduced to solve the problem of misconvergence of traditional successive iteration for new reactors such as SCWR. Key parameters have been calculated and analyzed to prove the feasibility and accuracy of the developed calculation codes. The study provides the basis for further study of stability and safety analysis for new SCWR.