Study on Coupling of NLSANMT and RELAP5/mod3.2

Based on the thermal-hydraulic code RELAP5/mod3.2,the coupling model of three-dimension space-time neutron kinetics and one-dimension thermal-hydraulic computation is established by the explicit method,and the three-dimension transient physical analysis model based on the show that the developed NLSANMT/RELAP5（mod3.2） program system is with better ability for core transient analysis,compared with RELAP5/mod3.2.nonlinear iterative Semi-Analytical Nodal code NLSANMT is transplanted.Proof-checking and computation of feedback coefficients and steady parameters of nuclear power reactor,and the simulation analysis of the uncontrolled accidental draw-out of one bundle of control rods prove the validity of the interface.The results show that the developed NLSANMT/RELAP5(mod3.2) program system is with better ability for core transient analysis, compared with RELAP5/mod3.2.