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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.
Tetsuya Mouri, Shuhei Maruyama, Taira Hazama, Takayuki Suzuki
Nuclear Technology | Volume 179 | Number 2 | August 2012 | Pages 286-307
Technical Note | Fission Reactors | doi.org/10.13182/NT12-A14099
Articles are hosted by Taylor and Francis Online.
The present technical note describes the evaluation of the isothermal temperature coefficient data obtained in the Monju restart core. As in the preceding evaluations on the criticality and the control rod worth, the best-estimate value and its uncertainty are evaluated as accurately as possible. Data obtained in the previous test are evaluated in the same level of detail.The measured data show that the fuel composition change from the previous test decreases the magnitude of the temperature coefficient by [approximately]8%. Through a sensitivity analysis, it is confirmed that the decrease is mainly brought by the composition of 241Pu and 241Am.The best calculation accuracy within the experimental uncertainty of 2% is attained with JENDL-4.0 for the previous core; however, such a good accuracy is not achieved for the restart core. A further experimental investigation is required to solve the dependence of calculation accuracy on the core configurations.