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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.”
R. F. Radel, G. L. Kulcinski
Fusion Science and Technology | Volume 47 | Number 4 | May 2005 | Pages 1250-1254
Technical Paper | Fusion Energy - Nonelectric Applications | doi.org/10.13182/FST05-A859
Articles are hosted by Taylor and Francis Online.
The effect of high temperature (700-1200°C) implantation of deuterium and helium in candidate fusion first wall materials was studied in the University of Wisconsin Inertial Electrostatic Confinement (IEC) device. Tungsten coated TaC and HfC ''foam'', single crystal tungsten, and high-emissivity tungsten coated ''foam'' were compared to previous tungsten powder metallurgy samples studied in the IEC device for the High Average Power Laser (HAPL) program. Scanning electron microscopy was performed to evaluate changes in surface morphology for various ion fluences at temperatures comparable to first wall temperatures. Single crystal tungsten was shown to exhibit less damage than polycrystalline samples at a fluence of 4×1016 He+/cm2. It was found that no significant deformations occur with deuterium implantation up to ~1018 D+/cm2 at 800°C on W-coated TaC and HfC foam samples. However, helium fluences in excess of 6×1017 He+/cm2 show extensive pore formation at 800°C and higher. These changes may have an impact on the lifetime of tungsten coatings on the first walls of inertial and magnetic confinement fusion reactors.