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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.
Kozo Katsuyama, Koji Maeda, Tsuyoshi Nagamine, Hirotaka Furuya
Nuclear Technology | Volume 169 | Number 1 | January 2010 | Pages 73-80
Technical Paper | Radiation Measurements and Instrumentation | doi.org/10.13182/NT10-A9344
Articles are hosted by Taylor and Francis Online.
Three-dimensional X-ray computer tomography (CT) images were successfully taken of a fast breeder reactor fuel assembly that had been irradiated to high burnup. The interior and outside of the fuel assembly can be clearly observed on any cross section from any angle. These images make it possible to analyze deformations and microstructural changes in the fuel pins and abnormalities in the fuel assembly. An analysis was made for 127 central voids, i.e., one in each fuel pin of the traverse cross section, and the void sizes were tentatively related to the linear heat rating. Compared with conventional nondestructive and destructive postirradiation examinations (PIEs), this X-ray CT technique has great advantages including acquiring large numbers of PIE data in a short time, reducing PIE costs, reducing the amounts of radioactive waste generation, and physically protecting nuclear materials.