Study on Flow and Heat Transfer Characteristics of Fuel Module under High Power Pulse Heating

In the Z Pinch fusion-fission hybrid reactor, the fusion neutron source is released in the form of pulse, and the intense pulse characteristic would exist in the energy releasing process of the fission fuel. On the basis of extracting the fuel module from the water cooling blanket, the flow and heat transfer characteristics were simulated and analyzed using Fluent program and lumped parameter method, respectively. The practicability of lumped parameter method in simulating pulse heating was demonstrated by Fluent program, and the effects of material thermophysical property on flow and heat transfer characteristics were analyzed. The calculation results show that lumped parameter method can be used in simulating the flow and heat transfer under pulse heating. The outlet temperature and flow rate would oscillate under pulse heating, and the oscillation could be weakened by increasing the heat capacity of fuel and decreasing the thermal conductivity of tube.