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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.
M. Tokitani, N. Yoshida, M. Miyamoto, T. Hino, Y. Nobuta, S. Masuzaki, N. Ashikawa, A. Sagara, N. Noda, H. Yamada, A. Komori, LHD Experiment Group
Fusion Science and Technology | Volume 58 | Number 1 | July-August 2010 | Pages 305-320
Chapter 7. Plasmas-Wall Interactions | Special Issue on Large Helical Device (LHD) | doi.org/10.13182/FST10-A10817
Articles are hosted by Taylor and Francis Online.
The Large Helical Device (LHD) has been equipped with movable- and fixed-type material probe systems. Characterization studies of surface modifications on plasma-facing components (PFCs) have been actively progressing by using these probes. After exposure of the PFCs to the plasma, various kinds of surface analysis were conducted. The first walls and divertor tiles of LHD are made of stainless steel and isotropic graphite (IG-430U, Toyo Tanso Co., Ltd.), respectively. They are frequently exposed not only to high-power pulsed main discharges but also to wall-conditioning processes such as glow discharge cleaning (GDC). Thus, the surfaces of the PFCs are drastically changed due to sputtering erosion, impurity deposition, and melting damage. Graphite divertor tiles are eroded primarily during the main discharges; the eroded carbon migrates and deposits on the first-wall surfaces, particularly near the divertor array. First walls are eroded mainly during GDC, which significantly changes the condition of the PFCs. During the main discharges, the majority of incidence particles to the first wall are energetic neutrals (CX neutrals) generated by charge-exchange collisions. Studies of the material damage caused by CX neutrals also have been done. In this paper, the characteristics of surface modifications of PFCs by means of material probe experiments and subsequent surface analysis are summarized.