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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.
Jeffery F. Latkowski, Jasmina L. Vujic
Fusion Science and Technology | Volume 33 | Number 3 | May 1998 | Pages 298-340
Technical Paper | doi.org/10.13182/FST98-A35
Articles are hosted by Taylor and Francis Online.
A consistent method for the comparison of environmental, safety, and health (ES&H) characteristics of fusion power plant designs is developed. Such comparisons enable identification of trends in fusion ES&H characteristics and can be used to increase the likelihood of fusion achieving its full potential with respect to ES&H characteristics.A large number of radiological hazard indexes are defined in three different categories of hazard: accidents, occupational and routine exposures, and waste disposal. Using a consistent set of computer codes, data libraries, and assumptions, these radiological hazard indexes are calculated and compared for five inertial and two magnetic fusion energy power plant designs.The results of the analysis are threefold: The utility of low-activation materials (LAMs) is confirmed, the tremendous potential for the use of a thick-liquid system for first-wall protection is validated, and the strong need for materials that can last for the lifetime of the power plant is shown.The conservative radionuclide release fractions that are used show that all but one of the designs has only a minute chance of producing any early fatalities during an accident. The need for remote maintenance in most designs is confirmed, and the possibility of disposing of most fusion wastes via shallow land burial (if the methodology of current regulations is applied to fusion wastes) is shown.The need for more research in LAMs and for the experimental measurement of radionuclide release fractions under accident conditions is emphasized.