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DOE-EM finishes cleanup of legacy Oak Ridge reactor lab site
The Department of Energy’s Office of Environmental Management announced that the 30-foot-long, 37,600-pound reactor vessel from Oak Ridge National Laboratory’s Low Intensity Test Reactor was shipped to EnergySolutions’ low-level radioactive waste facility in Clive, Utah, in late April.
Ryuji Yoshino, James K. Koga, Tatsuoki Takeda
Fusion Science and Technology | Volume 30 | Number 2 | November 1996 | Pages 237-250
Technical Paper | Special Section: Plasma Control Issues for Tokamaks / Plasma Engineering | doi.org/10.13182/FST96-A30753
Articles are hosted by Taylor and Francis Online.
A high toroidal eddy current induced in a vacuum vessel during plasma-current quench, Ip quench, results in errors in determining the vertical position of the plasma-current center, ZJ, calculated from standard linear regression sensor algorithms. These deviations result in a vertical displacement event (VDE) that must be avoided because of the expected severe damage on the first wall in tokamak fusion reactors like the International Thermonuclear Experimental Reactor (ITER). On the other hand, high ZJ calculation accuracy must be maintained at steady state to obtain reasonable plasma performance. Thus, real-time sensor algorithms for the calculation of ZJ applicable to the two cases of steady state and slow Ip quench are investigated. When a statistical method is applied to the ZJ calculation, its deviation from the actual ZJ cannot be completely reduced at the same time for both cases. On the contrary, a neural network demonstrates high accuracy in the calculation of ZJ for both cases, which enables real-time feedback control of ZJ during slow Ip quench, avoids VDE, and keeps reasonable plasma performance during steady state.