The work aims to understand the current design and application status of tritium transport packages both domestically and internationally and propose recommendations based on the experiences of foreign countries to facilitate the independent development of domestic transport packages and regulations. A survey and analysis of the design and application status of tritium transport packages used in fusion devices at home and abroad were conducted, highlighting key design concerns. It was recognized that the safest method for transporting tritium was in the form of metal tritium. Tritium transport packages for fusion devices were all designed as Type B(U) packages, with a loading capacity typically in the range of tens of grams of tritium. To mitigate the risks of tritium leakage and migration, multi-containment systems were incorporated into the design of these packages. Furthermore, considerations must be made for the decay of tritium, the production of helium-3 (3He), and the decay heat, which could lead to increased pressure and temperature. Therefore, it is recommended to pay attention to the research and development of tritium transport packages for fusion devices, along with the formulation of corresponding technical standards and regulatory guidelines based on international design experiences.