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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.
Martin R. Williamson, Laurence F. Miller, Indraneel Sen
Nuclear Technology | Volume 177 | Number 3 | March 2012 | Pages 413-420
Technical Paper | Radiation Measurements and General Information | doi.org/10.13182/NT12-A13484
Articles are hosted by Taylor and Francis Online.
A methodology for simulating a neutron detector's pulse-height spectra (PHS) utilizing semiempirical equations for the light yield nonproportionality of organic scintillators is described. Using these simulations, suitable material synthesis techniques are established for optimizing the performance of neutron scintillators. A MATLAB program suite was developed to automate the process of generating the PHS by pairing these semiempirical equations with results generated using Monte Carlo radiation transport code (MCNPX) particle track (PTRAC) output files. This is accomplished by first calculating the energy deposited in a detector from each charged-particle reaction product generated from a neutron absorption event by postprocessing the MCNPX PTRAC output files. The energy deposited from each charged particle is then used in semiempirical light yield equations to determine the fluorescent light energy output by each charged particle. Finally, the individual contributions from each charged particle are recombined to accurately simulate the pulse generated from the neutron absorption event.