The invention relates to the technical field of uranium-bearing waste treatment in production of uranium oxide powder and fuel pellets, in particular to a uranium-bearing material dissolution process control method. The method includes: starting a tail gas absorption system and controlling stability of tail-gas negative pressure; when tail-gas negative pressure reaches process requirements, adding deionized water and heating the same, and adding a uranium-bearing material when the deionized water is heated to designated temperature; after addition of the uranium-bearing material and a feed valve is closed, adding quantitative nitric acid; starting pressure-controlled automatic stirring, and performing gas stirring on a reaction medium in a dissolving tank; after dissolving reaction reaches the set time, sequentially stopping pressure-controlled stirring and operation of a heater, and sending out a reaction completion instruction through a PLC (programmable logic controller) module. By the arrangement, continuity, stability and the like in dissolving production are greatly improved, indicators of uranium concentration, acidity and the like are stable and controllable, degree of process automation is greatly improved, and labor intensity of technologists is alleviated.