The fuel assembly is an important component of the reactor,and the critical heat flux(CHF)is one of the most critical parameters that determine the performance of the fuel assembly.With reference to the parameters of helical cruciform fuel elements in the Nuclear Engineering Thermal-Hydraulic Laboratory of Shanghai Jiao Tong University,a 19-pin helical cruciform fuel assembly was designed and the CHF experiment was carried out.A measurement method for the CHF of uniformly heated full-length helical fuel rod bundle was developed.The CHF database of helical fuel assemblies was obtained,and the experimental results were analyzed.The results show that the critical power decreases linearly with the increase of inlet temperature,pressure and dryness,and increases with the increase of mass flow rate.A CHF prediction model for helical fuel assembly is established by introducing a circumferential non-uniform factor.The statistical distribution of experimental value(M)/predicted value(P)data presents normal distribution and is uniformly distributed around 1,which proves the reliability and accuracy of the relationship.The proposed experimental technique and model development method are universal,and can be applied to the study of CHF characteristics of similar helical fuel assemblies.
维普
万方数据
