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DNFSB spots possible bottleneck in Hanford’s waste vitrification
Workers change out spent 27,000-pound TSCR filter columns and place them on a nearby storage pad during a planned outage in 2023. (Photo: DOE)
While the Department of Energy recently celebrated the beginning of hot commissioning of the Hanford Site’s Waste Treatment and Immobilization Plant (WTP), which has begun immobilizing the site’s radioactive tank waste in glass through vitrification, the Defense Nuclear Facilities Safety Board has reported a possible bottleneck in waste processing. According to the DNFSB, unless current systems run efficiently, the issue could result in the interruption of operations at the WTP’s Low-Activity Waste Facility, where waste vitrification takes place.
During operations, the LAW Facility will process an average of 5,300 gallons of tank waste per day, according to Bechtel, the contractor leading design, construction, and commissioning of the WTP. That waste is piped to the facility after being treated by Hanford’s Tanks Side Cesium Removal (TSCR) system, which filters undissolved solid material and removes cesium from liquid waste.
According to a November 7 activity report by the DNFSB, the TSCR system may not be able to produce waste feed fast enough to keep up with the LAW Facility’s vitrification rate.
William E. Kastenberg, Clyde D. Newman
Nuclear Technology | Volume 97 | Number 2 | February 1992 | Pages 241-251
Technical Paper | Economic | doi.org/10.13182/NT92-A34619
Articles are hosted by Taylor and Francis Online.
A cost/risk framework is developed to compare waste management alternatives such as partitioning and transmutation (P-T) to the currently open light water reactor fuel cycle in the United States in which spent fuel will be buried in a geologic repository. This framework has utility for developing economic values associated with long-term risk and was originally developed as part of a system study to define and determine the scope of the driving features of a P-T scheme involving nonconventional (pyrochemical) reprocessing and a fast-spectrum reactor fueled primarily with minor actinides. A potentially significant benefit is shown to be obtainable in the form of reduced long-term repository health risks; although the primary risk reduction is derived from the destruction or selective packaging and disposal of 99Tc and 129I, the modification of probabilities associated with site-specific repository features or highly uncertain future events could affect these results. The potential benefits are represented as a cost stream and appear as a large annual investment available for the development and implementation of P-T. Preliminary results suggest further studies in selected areas; a particularly significant near-term health risk benefit is expected to arise from reduced uranium mining and purification activities associated with the closure of the currently open fuel cycle. Although the cost/risk framework was originally developed to evaluate a specific waste management concept, similar analyses can be used to evaluate other waste management schemes as well. Reprocessing of spent fuel to recover specific problem isotopes is an obvious possibility but may lack the overall flexibility engendered in P-T to address the complete spectrum of public concerns.