Abstract: The High Flux Engineering Test Reactor (HFETR) is loaded with complex geometry assemblies, taking on strong heterogeneity. These features call for more advanced core analysis and fuel management methodologies compared with traditional PWR. Based on the two-step method, a fuel management simulation platform HEFT was developed. In HEFT, the lattice code HEFT-lat has the abilities to describe complex assembly geometries of HFETR, whereby mitigate errors brought by geometrical approximations. DNTR, a triangular mesh nodal S_N method code, was employed to solve the transport equation. The good agreements between simulation results and experimental ones show that HEFT can meet the demand of engineering simulations.