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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.
Mark S. Jarzemba, James Weldy, English Pearcy
Nuclear Science and Engineering | Volume 131 | Number 2 | February 1999 | Pages 275-281
Technical Paper | doi.org/10.13182/NSE131-275
Articles are hosted by Taylor and Francis Online.
Two subcritical assemblies (consisting of a subcritical reactor plus a neutron emitter such as 252Cf) designed for conducting neutron activation analyses in the field are described. The size of the assemblies has been minimized (compared to conventional, graphite-moderated assemblies) to allow for field portability. Although less powerful than using a research reactor as the source of neutrons, these assemblies will provide an adequate source of neutrons for detecting gold concentrations in rock or soil samples down to the limits of economic importance. Using a field-portable source of neutrons eliminates the need for shipping samples back to the reactor for analysis, which may be important for reasons of sample security and measurement turnaround time. The two subcritical assemblies are composed of natural uranium metal as the multiplying material and high-density polyethylene as the moderator, and they have keff approximately equal to 0.8 for the smaller assembly (~692-kg assembly mass) and 0.9 for the larger assembly (~3059-kg assembly mass). The larger assembly was found to be more desirable from a neutronics standpoint; however, it may be too massive to maintain field portability. It was found that the optimal location for the irradiation facility (a 4.0-cm-high, 2.0-cm-diam right cylinder) in the subcritical assemblies is the grid location as close to the neutron emitter location as possible. It was also found that the total, epithermal plus thermal (i.e., neutron energy <0.5 eV), and thermal (i.e., neutron energy <0.05 eV) volume-averaged neutron fluxes were as follows (assuming a neutron emitter source strength of 109 n/s): 1.72 × 108, 4.47 × 107, and 2.15 × 107 cm-2s-1 for the smaller assembly, and 3.43 × 108, 9.09 × 107, and 4.37 × 107 cm-2s-1 for the larger assembly. Although the purpose for which the assembly was designed was for conducting neutron activation analyses for gold, the assemblies should also work equally well for analyzing sample compositions of other elements at both the bulk and trace levels.
