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Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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2024 ANS Annual Conference
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Glass strategy: Hanford’s enhanced waste glass program
The mission of the Department of Energy’s Office of River Protection (ORP) is to complete the safe cleanup of waste resulting from decades of nuclear weapons development. One of the most technologically challenging responsibilities is the safe disposition of approximately 56 million gallons of radioactive waste historically stored in 177 tanks at the Hanford Site in Washington state.
ORP has a clear incentive to reduce the overall mission duration and cost. One pathway is to develop and deploy innovative technical solutions that can advance baseline flow sheets toward higher efficiency operations while reducing identified risks without compromising safety. Vitrification is the baseline process that will convert both high-level and low-level radioactive waste at Hanford into a stable glass waste form for long-term storage and disposal.
Although vitrification is a mature technology, there are key areas where technology can further reduce operational risks, advance baseline processes to maximize waste throughput, and provide the underpinning to enhance operational flexibility; all steps in reducing mission duration and cost.
Leah Spradley, Mark Abkowitz, James H. Clarke
Nuclear Technology | Volume 169 | Number 2 | February 2010 | Pages 180-194
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT10-A9361
Articles are hosted by Taylor and Francis Online.
This paper focuses on how variations in commercial spent nuclear fuel shipment schedules have the potential to impact preclosure operations at the proposed repository for high-level waste at Yucca Mountain (YM) in Nevada. The analysis employs a simulation tool developed by the authors for modeling the packaging and thermal characteristics of the waste stream arriving at Yucca Mountain and is related to a study on the safety of the surface facilities that was also conducted by the authors using the simulation tool. The objective of the research is to gain a better understanding of how waste-stream variations affect surface facility throughput, defined as the rate at which packages are prepared for aging or emplacement in the surface facilities at YM. The basis for and adequacy of the preliminary surface facility throughput requirements are reviewed by evaluating throughput performance subject to various preclosure operating scenarios.Results indicate that under most scenarios, the preliminary design adequately accommodates the mean demand over the operating lifetime for the canister receipt and closure facility (CRCF) and receipt facility (RF) but not the wet handling facility (WHF). While results indicate that WHF demand is likely to be higher than capacity in many scenarios, it seems reasonable that dual-purpose cask and truck deliveries could be deferred to maintain WHF operations at near-capacity levels.Results also show a high potential for variability in annual throughput demand at the CRCF and RF that might result in system backups. In the event of bottlenecks, the facility with less demand can fulfill functional roles of one that is overburdened. The overlap of functional capability in facilities incorporates flexibility into the system. However, since throughput targets are named per facility, as opposed to functions of the system, the design goals of the system as a whole are obscured. An alternative design is proposed that is based on functional goals within the facilities, along with other recommendations.