Design study of a tritium transport package for future fusion reactors

The first design of a tritium transport package with large capacity and compact size, which can be applicable to tritium transport for International Thermonuclear Experimental Reactor (ITER) was developed. To verify that the package complies with the requirements for the BU type package stipulated in the IAEA regulation of transport packages, structural and thermal analysis were made for hypothetical accident conditions during transport. Structural analysis with the volumetric displacement method (VDM) method under conditions of 9 m drop test and thermal analysis with the ABAQUS code under conditions of 800°C×30 min thermal test showed that the package complied with the requirements for BU type transfer packages. An additional safety analysis was to confirm integrity of the confinement components when the package sinks in the deep sea of 6000 m in depth.