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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.
B. Richardson, J. King, A. Alajo, S. Usman, C. H. C. Giraldo
Nuclear Science and Engineering | Volume 187 | Number 1 | July 2017 | Pages 100-106
Technical Paper | doi.org/10.1080/00295639.2017.1292089
Articles are hosted by Taylor and Francis Online.
To validate an MCNP5 model of the Missouri S&T Research Reactor (MSTR), temperature and void effects on reactivity experiments were simulated and performed. We compared the keff of the modeled reactor mirroring the position of all control rods to the actual critical reactor (keff = 1.00000). In the simulation we modeled three different scenarios. In the first two scenarios, the reactor is modeled as isothermal at two different temperatures (measured experimentally near the core), and in the third scenario, we split the core into bottom and top parts and used interpolated values for the temperatures of both halves. The model predicted keff’s for the “critical reactor” between 1.00234 and 1.00248 (±0.00018) when using as temperature the experimental thermocouple readings at the top of the core and keff’s between 1.00296 to 1.00383 (±0.00018) when using the temperature of thermocouple readings at the bottom of the core. In the third experiment, a linear vertical temperature profile was included in the model (only top and bottom of the core), and the model predicted keff’s between 1.00218 and 1.00302 (±0.00018). The keff modeled and experimental values differed by as much as 0.40%. A void coefficient of the reactivity experiment was also simulated introducing a void tube in the model and the control rods made to mirror the critical experimental reactor with an identical void.