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Spent fuel recycling and conditioning topic of U.S.-Japan meeting
Officials with the Department of Energy’s Office of Environmental Management discussed spent nuclear fuel recycling and conditioning with counterparts from Japan during the 13th U.S.-Japan Technical Meeting of the Civil Nuclear Energy Research and Development Working Group, held recently in Santa Fe, N.M.
Kenneth M. Young
Fusion Science and Technology | Volume 57 | Number 3 | April 2010 | Pages 298-304
Technical Note | doi.org/10.13182/FST10-A9473
Articles are hosted by Taylor and Francis Online.
A demonstration tokamak is an essential next step toward a magnetic fusion-based reactor. One based on advanced tokamak plasmas is especially appealing because of its relative compactness. However, many plasma measurements will be required to provide the necessary signals to feed to ancillary systems to protect the device and control the plasma. This technical note addresses the question of how much intrusion into the blanket system will be required to allow the measurements needed to provide the information required for plasma control. All diagnostics will require, at least, the same shielding designs as planned for ITER, while having the capability to maintain their calibration through very long pulses. Much work is required to define better the measurement needs and the quantity and quality of the measurements that will have to be made, and how they can be integrated into the other tokamak structures.