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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.
Otasowie Osifo, Staffan Jacobsson Svärd, Ane Håkansson, Christofer Willman, Anders Bäcklin, Tobias Lundqvist
Nuclear Science and Engineering | Volume 160 | Number 1 | September 2008 | Pages 129-143
Technical Note | doi.org/10.13182/NSE160-129TN
Articles are hosted by Taylor and Francis Online.
Decay heat is an important design parameter at the future Swedish spent nuclear fuel repository. It will be calculated for each fuel assembly using dedicated depletion codes, based on the operator-declared irradiation history. However, experimental verification of the calculated decay heat is also anticipated. Such verification may be obtained by gamma scanning using the established correlation between the decay heat and the emitted gamma-ray intensity from 137Cs. In this procedure, the correctness of the operator-declared fuel parameters can be verified.Recent achievements of the gamma-scanning technique include the development of a dedicated spectroscopic data-acquisition system and the use of an advanced calorimeter for calibration. Using this system, the operator-declared burnup and cooling time of 31 pressurized water reactor fuel assemblies was verified experimentally to within 2.2% (1) and 1.9% (1), respectively. The measured decay heat agreed with calorimetric data within 2.3% (1), whereby the calculated decay heat was verified within 2.3% (1). The measuring time per fuel assembly was ~15 min.In case reliable operator-declared data are not available, the gamma-scanning technique also provides a means to independently measure the decay heat. The results obtained in this procedure agreed with calorimetric data within 2.7% (1).