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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.
T. Seki, T. Mutoh, R. Kumazawa, K. Saito, Y. Nakamura, M. Sakamoto, T. Watanabe, S. Kubo, T. Shimozuma, Y. Yoshimura, H. Igami, K. Ohkubo, Y. Takeiri, Y. Oka, K. Tsumori, M. Osakabe, K. Ikeda, K. Nagaoka, O. Kaneko, J. Miyazawa, S. Morita, K. Narihara, M. Shoji, S. Masuzaki, M. Goto, T. Morisaki, B. J. Peterson, K. Sato, T. Tokuzawa, N. Ashikawa, K. Nishimura, H. Funaba, H. Chikaraishi, N. Takeuchi, T. Notake, H. Ogawa, Y. Torii, F. Shimpo, G. Nomura, M. Yokota, C. Takahashi, A. Kato, Y. Takase, H. Kasahara, M. Ichimura, H. Higaki, Y. P. Zhao, J. G. Kwak, H. Yamada, K. Kawahata, N. Ohyabu, K. Ida, Y. Nagayama, N. Noda, T. Watari, A. Komori, S. Sudo, O. Motojima, LHD Experimental Group
Fusion Science and Technology | Volume 50 | Number 2 | August 2006 | Pages 186-191
Technical Paper | Stellarators | doi.org/10.13182/FST06-A1234
Articles are hosted by Taylor and Francis Online.
The long-pulse plasma discharge experiment is an important experiment in the Large Helical Device, which has a superconducting coil system and the capability of steady-state operation. The experiment of long-pulse plasma discharge was carried out using mainly ion cyclotron range of frequencies heating. The maximum plasma duration is 31 min and 45 s, and the total injected heating energy reached 1.3 GJ. Swing of the magnetic axis is adopted as an effective method to scatter the local heat load on the divertor plate during the discharge. The plasma was terminated abruptly by the influx of metallic impurities accompanied by a spark in the vacuum vessel.
