The safe transportation and storage of spent fuel are critical aspects of nuclear energy utilization. The storage capacity for spent fuel at nuclear power plants is typically 10–20 years. With the large-scale development of nuclear energy, the production of spent fuel is increasing annually, leading to a growing demand for spent fuel reprocessing. Therefore, the off-site storage and transportation of spent fuel is an inevitable development direction. To meet the growing demand for spent fuel transport containers, this paper investigates key issues in the shielding design of VVER spent fuel transport containers. It focuses on analyzing the characteristics of the source terms of components within the transport container, the determination of shielding materials, the application of flux-to-dose conversion coefficients, and the dose rate levels around the container. The research findings have been applied to the shielding design of this container to enhance its shielding performance and loading capacity, thereby further improving the container’s safety efficiency.