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Latest News
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.
Sungjin Kwon, Kihak Im, Jong Sung Park
Fusion Science and Technology | Volume 72 | Number 4 | November 2017 | Pages 737-746
Technical Note | doi.org/10.1080/15361055.2017.1350479
Articles are hosted by Taylor and Francis Online.
A pressurized water cooling divertor target applying the tungsten monoblock type has been primarily considered in the Korean fusion demonstration reactor (K-DEMO). The target peak heat flux locally concentrated around the striking point was set to 10 MW/m2 in K-DEMO divertor system. In a previous study [Im et al., IEEE Trans. Plasma Sci., Vol. 44, p. 2493 (2016)] the thermomechanical analyses for a high heat flux unit of K-DEMO divertor target applying reduced activation ferritic martensitic (RAFM) steel as heat sink material were carried out to verify the thermal and mechanical stabilities. The results of the thermomechanical analyses showed that the stabilities of the divertor target design applying the derived design parameters were close to the allowable limits, since the thickness of RAFM coolant tube was too thin due to the low thermal conductivity of RAFM steel. The aim of this study is to propose the structurally modified divertor concept switching the flowing path of coolant from poloidal direction to toroidal direction. By changing the flow direction, the design and material could be independently selected by the local intensity of the heat flux. The CuCrZr and RAFM steel were employed to the peak heat flux region and the non-peak heat flux region as a heat sink material, respectively. The effects of the modified concept were assessed by performing thermohydraulic analyses. The result showed that the modified concept more efficiently dissipated the heat flux compared to the conventional concept.