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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 Regnier, Olivier Litaize, Olivier Serot
Nuclear Science and Engineering | Volume 174 | Number 1 | May 2013 | Pages 103-108
Technical Note | doi.org/10.13182/NSE12-12
Articles are hosted by Taylor and Francis Online.
The average total prompt neutron multiplicity [nu with overbar] of 252Cf spontaneous fission is investigated as a function of the total kinetic energy TKE and the mass split of the fragments through the code FIFRELIN. This Monte Carlo device, already described in a previous work, aims at simulating the neutron evaporation from fission fragments. The observables and TKE and the light fragment mass AL are recorded from a sample of 107 fission events. The analyzed results show a value for the inverse of the slope [[partial differential][nu with overbar](TKE)/[partial differential]TKE]-1 equal to -11.0 MeV/n. In addition to this, the average number of neutrons per fission [nu with overbar](TKE, AL) is determined for every possible TKE and AL. For every fragment mass ratio, differences in behavior between [nu with overbar](TKE, AL) versus TKE and [nu with overbar](TKE) with no discrimination made with regard to AL are observed. Those differences are explained by the TKE dependency of fission yield. The approximation consisting of ignoring this TKE dependency of mass yield when calculating the [nu with overbar](TKE) slope is discussed. We estimate that such a calculation could lead to a significant bias on the absolute value of [partial differential][nu with overbar](TKE)/[partial differential]TKE and could explain the discrepancies between calculations found in the literature.
