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One of the problems in fullfing energy needs in Indonesia is marked by the low electrification ratio, which is 60%. Many researchs dan various studies of alternative energy has been conducting to solve these problems. One of them is nuclear energy. The development of nuclear power plant (NPP) is very rapid. Nowdays, many studies of 4th Generation nuclear reactor which focus on improving safety is conducted. The characteristic of some IV generation nuclear reactors is the use of molten salt as a coolant. The purpose of this study is to determine the heat transfer of molten salt in the natural circulation system for steady state analysis and transient characteristic with COMSOL Multiphysics method. The selected module is the Non-Isothermal FLow (NITF) module. This module is a combination of three basic equations, namely the continuity equation, the Navier-Stokes equation, and the dynamic equation of heat transfer in fluid. The simulation model measures 1.5 x 2 (m) with sodium (Na) as a fluid. The simulation demonstrates 4 conditions: 1) Steady state; 2) Transient I; 3) Transient II; 4) Heater Trip. The conditions of transient I, and transient II, show the system is still in a safe condition because the temperature value is still below the value of liquid sodium boiling and SS316 pipe melting point. In the heater trip condition, liquid sodium has a temperature drop to near freezing.