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North American construction is back—smaller and faster—at OPG’s Darlington
“The nuclear renaissance is real here,” said Ontario Power Generation’s Subo Sinnathamby on May 8, one year to the day after OPG secured a final investment decision to build the first of four planned BWRX-300 reactors at its Darlington nuclear power plant, and shortly after the new reactor’s foundation was lifted into place. “We got our license to construct in April and our [final investment decision] in May, and we’ve been off to the races since.”
T. N. Carlstrom
Fusion Science and Technology | Volume 48 | Number 2 | October 2005 | Pages 997-1010
Technical Paper | DIII-D Tokamak - Achieving Reactor Quality Plasma Confinement | doi.org/10.13182/FST05-A1055
Articles are hosted by Taylor and Francis Online.
DIII-D contributions to H-mode transition physics and power thresholds are reviewed. Two general approaches were pursued: (a) establishing scaling relations based on empirical observations and (b) acquiring a theoretical understanding of the physics of the transition. The interaction of experiment results and the development of theories over the early 1990s led to the highly successful and widely accepted model of shear suppression of turbulence by crossed electric and magnetic fields (E × B) as the cause of improved confinement in H-mode. Experimental studies have also examined parameters at the edge of the plasma in order to identify a control parameter for the transition and to test various theories of the transition. The effect of the direction of the [nabla]B drift on the H-mode power threshold is used as a tool to further understand the physics of the L-H transition. Results on DIII-D and other tokamaks have guided researchers to study turbulent generated flows as a possible trigger for the L-H transition. Access to H-mode is controlled by a power threshold, and it is important to predict the threshold for next-generation tokamaks. In addition to electron density and toroidal field dependencies, it is found that many other parameters affect the power threshold. Studies of plasma size, magnetic configuration, and neutral effects have been performed. DIII-D data have been used in an international tokamak database to help establish scaling relations to predict power thresholds in future devices.