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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.
David J. Loaiza, Glenn Brunson, Rene Sanchez, Ken Butterfield
Nuclear Science and Engineering | Volume 128 | Number 3 | March 1998 | Pages 270-277
Technical Paper | doi.org/10.13182/NSE98-A1955
Articles are hosted by Taylor and Francis Online.
The delayed neutron activity resulting from the fast induced fission of 235U and 237Np has been studied. The six-group decay constants, relative abundances, and absolute yield of delayed neutrons from fast fission of 235U and 237Np were measured using the Godiva IV fast assembly at the Los Alamos Critical Experiments Facility. The absolute yield measured for 235U was 0.0163 ± 0.0008 neutron/fission. This value compares very well with the well-established Keepin absolute yield of 0.0165 ± 0.0005. The absolute yield value measured for 237Np was 0.0126 ± 0.0007. The measured delayed neutron parameters for 235U are corroborated with period (e-folding time) versus reactivity calculations.
