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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.”
M. Fujiwara
Fusion Science and Technology | Volume 27 | Number 3 | April 1995 | Pages 58-70
Overview Paper | doi.org/10.13182/FST95-A11947047
Articles are hosted by Taylor and Francis Online.
Recent research has made significant progress for the plasma confinement in helical systems. Experiments have been carried out in W7AS, CHS, ATF, H-E and others. The plasmas, whose electron temperature is around 2–3keV, ion temperature is 1 keV and density is 2–3×1020 m-3, are well confined with the energy confinement time τ E =10–40ms and the stable beta value reaches at < β >> 2% (β (0)=7%)[1]. The obtained scalings for the global energy confinement time such as LHD, GRB(Gyro-Reduced Bohm), L-G(Lackner-Gottardi) scalings are comparable with the tokamak L-mode scaling in the above parameters' range. The improved confinement modes are also explored in helical systems as H mode or the control of plasma profile.
In this paper, firstly present experimental results are reviewed on the confinement, MHD equilibrium/stability beta limit, and secondly the outline of LHD and W7X program is described.
Finally, is discussed the feasibility of helical systems as a fusion reactor, based on the present experimental results.