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Fusion Science and Technology
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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.
Jong Woon Kim, Cheol Woo Lee, Young-Ouk Lee, Dong-Won Lee, Seungyon Cho
Fusion Science and Technology | Volume 68 | Number 3 | October 2015 | Pages 652-656
Technical Paper | Proceedings of TOFE-2014 | doi.org/10.13182/FST14-966
Articles are hosted by Taylor and Francis Online.
The discrete ordinates code under development by KAERI uses an unstructured tetrahedral mesh, and can thus be applied to solve the radiation transport in a complicated geometry. In addition, the geometry modeling process has become much easier because computational tetrahedral meshes are generated based on the CAD file by Gmsh. This program has been enhancing its performance and adding functions for each application.
In previous research, it was applied in a neutronics analysis for the Korea Helium Cooled Ceramic Reflector (HCCR) TBM. The total neutron fluxes were compared with the results from MCNPX and showed good agreement.
In this paper, we applied our program to a simplified ITER model which is a 40-degree toroidal segment. The zone averaged total fluxes were compared with those of MCNPX, and total neutron flux distribution was visualized in a three-dimensional system domain.
