Hydrogen-boron (\mathrmp-^11\mathrmB) fusion is widely regarded as one of the most promising candidates for advanced magnetic confinement fusion due to its remarkable advantages, including negligible neutron damage, abundant and non-radioactive fuel resources, and the potential for highly efficient direct energy conversion through energetic α particles. However, existing integrated simulation codes generally lack dedicated physics modules for \mathrmp-^11\mathrmB reactions, limiting their capability to support the parametric design and physics analysis of such advanced-fuel devices. To address this issue, a 0.5-dimensional (0.5-D) integrated simulation framework named CJK was developed in this study by coupling a specific \mathrmp-^11\mathrmB fusion module, achieving a good balance between physics completeness and computational efficiency. Benchmark analyses against the mainstream international fast-computation code METIS show good agreement in key plasma physics quantities, such as the ion temperature profile, safety factor profile, bootstrap current, and plasma beta. Although numerical differences exist in the \mathrmp-^11\mathrmB fusion power, the computational results from both codes remain on the same order of magnitude and exhibit consistent variation trends, which verifies the reliability and applicability of the CJK code in \mathrmp-^11\mathrmB fusion simulations. Relying on the CJK code, a systematic numerical investigation was conducted targeting ENN’s EHL-2 spherical tokamak (ST), which is currently under construction. The underlying physics mechanisms affecting the \mathrmp-^11\mathrmB fusion power were thoroughly analyzed by scanning key operational parameters. The simulation results indicate that, regarding macroscopic electromagnetic parameters, increasing the plasma current (I_\mathrmp) enhances confinement, raises the ion temperature, and significantly suppresses the first-orbit loss fraction of energetic α particles; meanwhile, enhancing the toroidal magnetic field (B_\mathrmt) helps reduce transport losses, further increasing the fusion power. In terms of auxiliary heating, the neutral beam injection (NBI) energy should not be overly high to ensure the dominance of thermonuclear fusion in the bulk plasma and avoid excessive beam-target reactions, while an excessively large NBI tangency radius leading to off-axis deposition causes a drastic drop in the core ion temperature and fusion power. Furthermore, optimizing the deposition location of electron cyclotron wave (ECW) heating (with an appropriate power) around \rho\approx 0.35 yields favorable current and q profiles, which strengthens α particle confinement. Concerning plasma geometry and composition, a larger elongation (κ) expands the plasma volume but slightly degrades α particle confinement, whereas the boron-to-hydrogen density ratio (f_\mathrmBH) exhibits a non-monotonic relationship with the effective fusion power due to fuel dilution. Based on these comprehensive analyses, a synergistic optimization strategy for \mathrmp-^11\mathrmB fusion performance in the EHL-2 device is proposed. Within engineering and physics constraints, a \mathrmp-^11\mathrmB fusion power of up to 200\; \mathrmW can be achieved by utilizing a higher plasma current (3\; \mathrmMA), a toroidal field (3\; \mathrmT), and an NBI power (14\; \mathrmMW), synergistically combined with an optimized elongation (\kappa\approx 2.1), NBI beam energy (<130\; \mathrmkeV), ECW heating (\rho\approx 0.35,\; P_\mathrmECW\approx 5\; \mathrmMW), and a boron-to-hydrogen ratio (0.15 \sim 0.20). Finally, considering that the EHL-2 device is currently under construction, the theoretical predictions and parameter optimization in this study will serve as crucial predictive guidance for future physics experiments. Once the device is officially built and enters the initial discharge phase, future work will benchmark the simulation predictions against actual discharge data. Relying on abundant experimental data, the empirical physics models and energy confinement scaling laws for ST and \mathrmp-^11\mathrmB plasmas in the current code will be continuously modified and refined. This will enable more accurate numerical simulations to support the design and operation of subsequent physics experiments, ultimately laying a solid foundation for the commercialization of \mathrmp-^11\mathrmB fusion through deep theoretical-experimental iterative cross-validation.