Study on Neutronic-Thermohydraulic Coupling Calculation of SCWR

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.