Nuclear fusion energy is a clean and safe energy resource with huge potential. Tungsten is the primary candidate for plasma facing materials (PFMs) in future nuclear reactors because of its high melting point, high thermal conductivity and high resistance to sputtering and erosion. However, the interaction between tungsten and helium plasma generated by deuterium-tritium nuclear reactions will result in the degeneration of tungsten through helium blistering in tungsten. The solubility of helium in tungsten is low, and it tends to aggregate at grain boundary, phase boundary, vacancies and dislocations, thus forming helium bubbles. These bubbles will lead to microstructure changes of surface and bulk phases, as well as a decrease in mechanical properties, which seriously affects the service life of material. Limited by experimental techniques, some basic problems for the growth of helium bubbles in tungsten are not clear, for instance, how the helium clusters migrate, and nucleation mechanisms. The study of complex helium bubble formation, evolution and its underlying mechanism in tungsten PFM necessitates advanced experimental techniques. Traditional methods such as ion implantation, scanning electron microscope and transmission electron microscope are inadequate for this task. Therefore, we propose the helium ion microscope method to investigate the aforementioned several aspects of helium in tungsten in situ and real-time. Here, a helium irradiation experiment is performed by helium ion microscope (HIM), featuring nanostructure fabrication, ion implantation and microscopic imaging. The HIM can generate an ion beam with energy in a range of 0.5-35 keV and an flux upto 10²⁵ ions/m²/s. In the process of helium ion implantation, we observe in situ and real time the helium blistering and the morphological evolution on tungsten surface, in order to capture the helium implantation-induced microscopic damage evolution on tungsten surface and subsurface. From the results of in situ HIM experiments, it is believed that a strong orientation dependence of blistering is observed with the blister occurring preferentially on the surface of grains with normal direction close to (111), and surface blistering of tungsten is directly related to cracks immediately below the surface. The present study demonstrates that the HIM is a powerful tool for investigating the helium blistering behavior in tungsten and provides valuable experimental data and reference for designing PFMs.