Toroidal Alfvén Eigenmodes (TAE) are global MHD instabilities that can be excited in fusion devices by energetic particles, such as those produced by neutral beam injection or fusion reactions. Their presence can significantly enhance the radial transport of fast ions, leading to increased particle losses. Understanding and controlling TAE-driven transport is crucial for optimizing confinement in future experiments like ITER and the Divertor Tokamak Test (DTT), where minimizing EP losses is essential for sustaining efficient plasma heating and stability. In this paper, we investigate the interaction between 510 keV fast ions injected by the neutral beam injector system in DTT and TAE modes through numerical simulations using the Hamiltonian guiding-center code ORBIT. Additionally, we estimate the heat flux at the separatrix by mapping the deposited power by lost energetic ions.