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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.
J. H. Kim, B. T. Min, I. K. Park, S. W. Hong
Nuclear Technology | Volume 169 | Number 3 | March 2010 | Pages 239-251
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT169-239
Articles are hosted by Taylor and Francis Online.
Three triggered steam explosion experiments using corium melts of various compositions were performed in the TROI facility. The interaction vessel was 0.3 m in diameter. The melt compositions were 70:30 (UO2:ZrO2) corium, pure zirconia, and partially oxidized corium (UO2:ZrO2:Zr:SS = 53.91:23.09:12.00:11.00 in weight percent). The test with 70:30 corium was performed with a 0.95-m-deep water pool under an elevated pressure of 0.205 MPa, while the others were performed with a 1.3-m-deep water pool under atmospheric pressure. The water temperature was maintained at room temperature. The melt mass released to the water pool was [approximately]10 kg for each test. The test with 70:30 corium resulted in a triggered steam explosion, considering the long duration of the dynamic pressure and the large amount of fine debris. The dynamic pressure trace from the steam explosion seemed to be superimposed on that from the external trigger. The test with pure zirconia led to multiple spontaneous steam explosions before any external triggering. The zirconia melt confirmed its explosivity. The spontaneous steam explosion with pure zirconia seems not to be affected by the water depth and diameter of the interaction vessel. The test with partially oxidized corium also resulted in a spontaneous steam explosion before an external triggering. These results are different from the previous TROI tests with 80:20 corium in a narrow interaction vessel of 0.3-m diameter, in which no spontaneous steam explosions occurred. The geometry of the interaction vessel used in these tests does not seem to influence the occurrence of a steam explosion, but the corium composition does affect the triggerability of it.
