This paper presents a systematic and integrated design for a high fusion triple product operational scenario on the HL-3 tokamak, establishing a robust physical and engineering foundation for its planned deuterium-tritium (D-T) experiments between 2027-2030. The fusion triple product (the product of ion density n_i, ion temperature T_i, and energy confinement time \tau_E) serves as a core metric for evaluating tokamak plasma performance, with clear physical significance as it directly relates to the fusion gain factor Q (ratio of fusion output power to input power). Achieving plasma "ignition" or self-sustained burning requires the triple product to exceed the Lawson criterion threshold (approximately 3 - 5 \times 10^20 keV \cdot s \cdot m^-3 for deuterium-tritium reactions). Therefore, pursuing high triple product operation represents not only a critical scientific objective in tokamak plasma physics but also a direct demonstration of the scientific feasibility of fusion energy.To obtain a feasible operational scenario with a triple product exceeding n_i \cdot T_i \cdot \tau_E=1 \times 10^20 keV \cdot s \cdot m^-3, this research innovatively constructs a comprehensive simulation workflow. This approach integrates parameter scanning, integrated modeling, instability analysis, and divertor physics assessment through iterative optimization to comprehensively predict the high-parameter operational states of the HL-3 device. Methodologically, the process begins with basic configuration design using EFIT and 0.5D parameter scanning with METIS to determine feasible ranges for plasma current, magnetic field, density, and heating power. This is followed by 1.5D integrated modeling using OMFIT, which combines EFIT for magnetic equilibrium, ONETWO for heating and current drive, TGYRO for transport calculations, and EPED1-NN for pedestal region analysis to obtain self-consistent plasma equilibria and profile distributions. Finally, magnetohydrodynamic (MHD) instabilities are evaluated using CLT, MARS, and ELITE codes, while SOLPS-ITER calculates divertor heat loads to ensure engineering feasibility.The results demonstrate that under conditions of I_p=2.0 MA, B_T=2.2 T, NBI heating power P_NBI=3 MW, and H_ITER98,y2=1.14, a high-performance operational mode with a core triple product of n_i \cdot T_i \cdot \tau_E=1.02 \times 10^20 keV \cdot s \cdot m^-3 can be achieved. This scenario employs a high-density (line-averaged density n_bar=9.26 \times 10^19/m^3, Greenwald fraction n_bar/n_GW=0.61), low-heating-power strategy, yielding excellent parameters including core electron density n_e(0)=11.53 \times 10^19/m^3, ion temperature T_i(0)=3.22 keV, electron temperature T_e(0)=3.16 keV, normalized beta \beta_N=1.65, and minimum safety factor q_min=1.02. In-depth MHD instability analysis reveals that the scenario effectively avoids internal kink modes due to qmin>1; tearing modes (TM) and neoclassical tearing modes (NTM) remain stable without growth over 1200–1400 Alfvén times; resistive wall mode (RWM) analysis shows the operational beta (\beta_N=1.65) remains well below both no-wall (1.976) and ideal-wall (2.25) limits, ensuring stability; edge-localized modes (ELMs) reside in the marginally stable region (\gamma/(\omega^*/2)=0.5-1.5), with the most unstable toroidal mode number around 25, yet distant from the unstable region, suggesting small or no ELMs are expected during experiments, which is beneficial for maintaining stable plasma parameters. Divertor heat load calculations indicate a peak heat flux not exceeding 1.5 MW/m^2, significantly below the engineering material limit for the lower divertor of 7 MW/m^2; a target plate electron temperature of approximately 16 eV indicates no detachment, but Z_eff distribution analysis confirms that physical-chemical sputtering in the divertor will not increase the core impurity content.This research not only provides detailed procedural recommendations and theoretical support for HL-3's pursuit of high-parameter operation but also accumulates valuable experience for advanced operational scenarios in ITER. Through systematic simulation and analysis, the study confirms HL-3's capability to achieve a triple product at the 10^20 KeV \cdot s \cdot m^-3 level, establishing a solid foundation for subsequent deuterium-tritium experiments and contributing significant scientific and engineering value to the advancement of magnetic confinement fusion energy development.