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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.
Gasper Zerovnik, Luka Snoj, Matjaz Ravnik
Nuclear Science and Engineering | Volume 163 | Number 2 | October 2009 | Pages 183-190
Technical Paper | doi.org/10.13182/NSE163-183
Articles are hosted by Taylor and Francis Online.
We demonstrated the use of combinatorial methods to optimize the filling of spent nuclear fuel (SNF) in metal canisters for final deep SNF repository, according to the maximal allowed thermal power per canister Pmax and the limit of n = 4 spent-fuel assemblies per canister. As a next step, the deposition time can be optimized by minimizing the required number of canisters M and the interim storage time. The method has been tested in detail for a typical pressurized water reactor (PWR), nuclear power plant (NPP) Krsko, SNF for different numbers of reactor cycles and different Pmax. The results show that the time interval between the last reactor cycle and the optimal deposition time varies between 3 and 30 yr for a typical PWR. The most significant contribution to the uncertainty of the calculated SNF decay heat (thermal power) is due to inaccurate cross sections taken from generic cross-section libraries. The quality of the results was verified by comparing the calculated M to the theoretical lower boundary Mmin. The idea behind the optimization method is universal and thus can be implemented for any SNF, canister, and repository design.