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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.
Harry J. Reilly, Lawrence E. Peters, Jr.
Nuclear Technology | Volume 11 | Number 1 | May 1971 | Pages 89-95
Technical Paper | Shielding | doi.org/10.13182/NT71-A30905
Articles are hosted by Taylor and Francis Online.
A calorimeter was made to determine the relative amount of gamma heating in watts per gram in different materials as a function of thickness and atomic number. The experiment was performed in the NASA Plum Brook Mockup Reactor, which has a typical light-water test reactor gamma-source spectrum. Carbon, aluminum, zirconium, tin, and lead specimens in slab geometry were irradiated. The results showed no significant difference in the gamma heating in carbon and aluminum, but the heating in the other materials was greater than that in aluminum and carbon. The smaller thicknesses had the greater heating. The calorimeter was also used to determine the gamma-heating effect in an irradiation experiment mockup having cylindrical geometry. The result showed good agreement with an expected value obtained from the slab geometry data. A theoretical analysis of the relative gamma heating was made using a one-dimensional multigroup transport program. It was concluded that the analysis and measurements agreed qualitatively and that quantitative differences were attributable mostly to geometrical effects. The results of this study are believed to be applicable to both nuclear reactor experiment designs and other reactor problems.