The invention provides a device and method for quickly recovering deuterium and tritium in fusion reactor discharged ash gases. The device is divided into a main path and a branch path according to effects and necessities of various units in treatment processes. The main path only comprises a cryogenic pump and a Pd alloy film separating unit, and 96% or more deuterium and tritium fuels in the discharged ash gases can be recovered by virtue of the two units. The method for quickly recovering deuterium and tritium in the fusion reactor discharged ash gases is short in treatment time, and better meets requirements for quick recovery of the deuterium and tritium fuels; and meanwhile, the recovery process is simplified, which is conducive to reduction of the retention volume of tritium in a system, thereby avoiding impurity gases from causing adverse effects on a Pd alloy film separator. Moreover, a small amount of deuterium and tritium not recovered by the main path are recovered by the branch path, thereby ensuring relatively high recovery efficiency. The device and method for quickly recovering deuterium and tritium in the fusion reactor discharged ash gases have the advantages of short treatment cycle, simple process, high recovery rate, good system stability, long service life and the like, and can meet design requirements of existing fusion reactors.