As an alternative to the traditional PUREX/UREX process for recycling spent nuclear fuel (SNF), a new process is being developed that utilizes hydrogen peroxide to dissolve SNF in aqueous carbonate solutions. Some of the primary benefits of the new peroxide promoted carbonate process include a smaller footprint, fewer separations steps, elimination of hazardous organic waste, and enhanced proliferation resistance by elimination of the pure plutonium stream produced in the PUREX/UREX process. This presentation will highlight our recent advances in developing an alkaline-based alternative for SNF reprocessing, including recent results involving dissolution rates, actinide partitioning, and separation factors for key short-lived fission products.