The divertor detachment and heat flux control under high-confinement H-mode conditions in tokamaks represent critical physical challenges in current magnetic confinement fusion research. Understanding the influence of detachment on H-mode boundary transport physics, particularly its compatibility with core confinement, is central to resolving divertor detachment physics. In this study, experimental results on divertor detachment and core confinement compatibility in H-mode plasma from the HL-2A tokamak are presented. On the objective magnetohydrodynamic framework for integrated tasks (OMFIT) integrated modeling platform, a novel neural network-based fast integrated modeling method for the divertor target region is developed by integrating a new edge neural network module (Kun-Lun Neural Networks, KLNN) to enhance divertor, scrape-off-layer and edge pedestal fast prediction capability. For the first time, this method is used to conduct integrated simulations of divertor detachment and core confinement compatibility in HL-2A discharge #39007 under high-confinement mode. The simulation results are validated with experimental measurements, demonstrating that they are well consistent. Further analysis reveals that in HL-2A H-mode detachment scenarios, turbulent transport in the core region ( 0.1 < \rho \leqslant 0.5 ) with high poloidal wave numbers (k_\theta \rho _\mathrms > 1 ) is dominated by ion temperature gradient (ITG) mode, while electron-driven turbulence prevails in the region (0.5 < \rho \leqslant 0.7) . In the boundary region, electron turbulence dominates at low normalized poloidal wave numbers ( k_\theta \rho _\mathrms < 2 ), whereas ITG modes become predominant at higher wave numbers ( k_\theta \rho _\mathrms > 2 ), accompanied by minor electron turbulence contributions. The research results of this work provide a certain foundation for integrated simulation and experimental verification in the study of core-edge coupling physics in tokamak devices and some insights for understanding detachment-compatible H-mode scenarios in the next-step fusion devices.